ML20054H217

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Public Version of Weekly Info Rept for Wk Ending 820611
ML20054H217
Person / Time
Issue date: 06/16/1982
From: Rehm T
NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To:
References
WIR-820611, NUDOCS 8206230118
Download: ML20054H217 (52)


Text

-

f 6.~

June 16, 1982 f

For:

The Commissioners From:

T. A. Rehm, Assistant for Operations, Office of the ED0

Subject:

WEEKLY INFORMATION REPORT - WEEK ENDING JUNE 11, 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 Mater.ial Safety and Safeguards C

Inspection and Enforcement D

Nuclear Regulatory Research E

Executive Legal Director F*

International Programs G

State Programs H

Resource Management I*

Analysis and Evaluation of Operational Data J*

Small & Disadvantaged Business Utilization & Civil Rights K*

Regional Offices L

CRGR Monthly Report M*

Executive Director for Operations N*

Items Addressed by the Commission 0

  • No input this week.

/ T. A. Rehm, Assistant for Operations Office of the Executive Director for Operations FOR SUBSCRIBERS ONLY

Contact:

T. A. Rehm, EDO 492-7781 8206230118 820616 PDR COMMS NRCC WEEKLYINFDREPT PDR

I HIGHLIGHTS OF WEEKLY INFORMATION REPORT Week Ending June 11, 1982 Calvert Cliffs i

On June 3 at 7 AM, an incident occurred which resulted in the temporary loss of all (three) diesel generators. Approximately one hour later two generators were declared operable. The cause of the incident was related to the paralleling of the diesel generators with buses that were being powered from an off-site source. The licensee is investigating.

R.E. Ginna On June 3, NRC met with Rochester Gas & Electric Corporation (RG&E) and Westinghouse (W) to discuss the recent Loose Part Monitor System (LPMS) alarms. RG&E postulates that the alarms are a result of thermal transients experienced by one or more of the components in this area rather than by a foreign object interacting with the steam generator tubes.

NRC recommended visual inspections during the outage planned for October 1982.

In the interim, RG&E will continue to monitor closely'.the LPMS.

9 North Anna Unit 2 North Anna commenced the second cycle of power operations on June 2 after a 90-day refueling outage. Actions.during the outage included:

1) fuel loading; 2) steam generator inspection; and 3) scheduled inservice inspection.

Low Level Waste Storage - TVA The staff has issued its Environmental Impact Appraisal and Safety Evaluation Report on TVA's application to store onsite low level radioactive waste generated at its Browns Ferry Nuclear Power Plant.

Safeguards Reform Recent studies indicate that it may be exceptionally difficult to sabotage an independent spent fuel storage installation. A generic issue paper has been developed as part of an effort to reform the physical security requirements for these installations and reduce unnecessary regulatory burden.

Retransfer from France to Japan IP has received for advance review a partial DOE analysis of a proposed transfer of 105 kilograms of plutonium recovered at La Hague from Japanese spent fuel of U.S. origin. This would be the first transfer of separated plutonium outside of EURATOM since passage of the NNPA of 1978.

NRC will prepare its own analysis.

Salem Units.1 and 27 The 41-day strike of union work rs!sas. ended and members started to return to work on June 11, 1982. The licensee and NRC will monitor workers to assure no hostilities against the safe operation of the plants.

s

=

OFFICE OF ADMINISTRATION Week Ending June 11, 1982 ADMINISTRATI'ON'0F THE' FREEDOM OF INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request

  • Initial Decision Received 290 13 Granted 218 0

Denied 34 6

Pending 38 7

ACTIONS THIS WEEK Received Richard A. Udell, Requests 19 categories of documents regarding Critical liass nuclear reactor events and safety problems.

Energy Project (82-261)

(NRC employee)

Requests four categories of documents pertaining (82-262) to agreements between NRC management and the NTEU regarding the, FWP Advisory Comittee.

Richard A. Udell, APPEAL TO THE ED0 for draft NUREG-0844, " Resolution Critical Mass of Unresolved Safety Issues A-3, A-4, and A-5 Energy Project Regarding Steam Generator Tube Integrity."

(82-A-6-82-210)

Bill Lodge, APPEAL TO THE COMMISSION AND TO THE ED0 for The Dallas the denied documents regarding draft inspection flornina flews and investigation reports, complaints submitted (82-A-7-82-193) to the flRC, and the identity of all persons present at a February 12, 1982 meeting regarding the Hayward Tyler Pump Company; copies of all documents referring to Marcus Rowden since June 1977; and copies of I&E Reports 81-12 and 81-20 for Comanche Peak.

Christopher M. McMurray, APPEAL TO THE ED0 for the denied documents Kirkpatrick, Lockhart, regarding eight categori.es of records relating Hill, Christopher & Phillips to the Shoreham plant.

(82-A-8-82-176)

CONTACT:

J. M. Felton 492-7211 ENCLOSURE A

2 1

Received, Cont'd Dudley Thompson, APPEAL TO THE EDO for the proposed civil penalty Dudley Thompson and order actions received from Regional offices Associates during the period January - April 1982, with (82-A-9-82-207) the exception of enforcement actions 82-43 and 82-50.

Granted Joseph Gallo, In response to a request for three categories Isham, Lincoln of records relating to Inv.itation for Bid (IFB) 1

& Beale No. RS-SECY-82-471, " Stenographic Reporting' (82-142)

Services," made available 15 documents, Kathy Doi, In response to a request for documents relating Critical Mass to the cancellation, postponement, termination or Energy Project deferral of nuclear plant construction since (82-204) 1/1/80, made available 59 documents.

Informed the requester additional documents subject to this request are already available at the PDR.

John W. Sullivan In response to a request for investigation reports (82-217) relating to the improper, illegal or inadvertent disposal of radioactive wastes at sea or in the Great Lakes, informed the requester we have rbferred two documents to the Public Health Service for their disclosure determination and direct response to him.

I Robert L. Boyer In response to a request for copies of four (82-227) specific NUREG reports and the NRC's 1981 Annual Report, made available copies of.the !!LREG reports.

Informed the requester the Annual Report 1s not yet available for distribution.

l M. Lyle Kincheloe, In response to a request for the non-proprietary General Research versions of technical proposals submitted in Corporation response to PEP No. PS-NMS-82-026 by Science l

(82-234)

Applications', Inc. and Roy F. Weston, Inc.,

made available a copy of the requested records.

(NRC employee)

In response to a request for four categories of (82-242) documents pertaining to NRC Vacancy Announcement 82-1589, made available 13 documents.

Robin L. Deal,

In response to a request for a list of the 514 Chem-Nuclear licenses issued by the NRC to components of the Systems, Inc.

Department of Defense, made avai.lable a computer (82-244) printout list of D0D licensees.

ENCLOSURE A

\\

3 Granted, Cont'd d

Karen R. Smith, In response to a request for all disclosable fledtronic, Inc.

information relating to any and all Government (82-249) contracts with ARC 0 regarding the dev lopment of nuclear batteries and documentation pertaining to the contract designated NUMEC, informed the requester the NRC has no documents subject to this request. Suggested that she contact the Department of Energy.

(NRC employee)

In response to a request for all official (82-254) charters for the Federal Women's Program Advisory Comitt'ee and the charter referenced in a meeting on May 26, 1982, made available three documents.

John W. Sullivan In response to a request for a copy of seven (82-259) listed NUREG reports, made available access to these reports.

Denied (An individual requesting In response to a request for three categories information about himself) of records on himself, made available one (82-209) document.

Denied 13 documents in their entirety pursuant to exemption (k)(2) of the Privacy Act and exemptions (5) and (7)(A) of the F0IA.

Denied three transcripts of Cominission meetings in their entirety pursuant to exemption (3) of the F0IA and exemption (5) of the Government in th'e Sunshine Act.

Andrea K. Wilson In response to a request for all correspondence (82-223) between Dow Chemical Company and the NRC relating to the incineration of laboratory wastes contaminated with low level radiation in 1974, made available six documents.

Denied portions of two documents, the disclosure of which would constitute a clearly unwarranted invasion of personal privacy.

ENCLOSURE A

h t

DIVISION OF CONTRACTS ITEMS OF INTEREST WEEK ENDING JUNE 11,1982 RFP ISSUED RFP NO.: RS-NMS-82-044/045 TITLE: " HYDR 0GE0 LOGIC INVESTIGATIONS OF THE BASATT WASTE ISOLATION" DESCRIPTION: Provide hydrogeological assistance in the preparation and review of BWIP Site Characterization Report (SCR) and in the production of NRC's Site Characterization Analysis (SCA).

PERIOD OF PERFORMANCE:

Fifteen (15) months SPONSOR: NMSS STATUS: RFP issued June 10, 1982.

June 21, 1982 proposals due RFP N0.: RS-0RM-82-318 TITLE: " KEYPUNCH AND VERIFICATION SERVICES" DESCRIPTION: To provide keypunching and 100% verification of EAM cards.

PERIOD OF PERFORMANCE: One year from contract effective date SPONSOR: Office of Resource Management STATUS: Letter RFP issued on June 4,1982 to Information Systems and Networks Corporation of Chevy Chase, Maryland.

PROPOSALS UNDER EVALUATION RFP N0.: RES-82-006 TITLE: "NEMAHA RIDGE SEISM 0 GRAPHIC NETWORKS" DESCRIPTION:

Install, operate, and analyze the data from seismographic networks in the Nemaha Ridge area.

PERIOD 0F PERFORMANCE:

3 years SPONSOR: RES STATUS:

Final Evaluation Report received on June 8,1982. Contracts mailed to contractors on June 10, 1982.

RFP N0.: 01E-82-249 TITLE: " TECHNICAL ASSISTANCE TO SUPPORT IE PERSONNEL IN THE INVESTIGATION OF INCIDENTS" DESCRIPTION: Technical and Engineering assistance to 01E personnel in performing inspections or technical evaluations of facilities.

PERIOD 0F PERFORMANCE: 2 years SPONSOR: OIE STATUS: The competitive range has been established and negotiations are scheduled for week of June 14-June 17,1982.

ENCLOSURE A

t CONTRACTS CLOSED-00T i

NRC-10-81-410

FEDSIM, 6/7/82 Department of the Air Force NRC-02-81-065 S. S. Papadopulos &
  • 6/7/82 Associates, Inc.

NRC-03-79-160 Woodward-Clyde Consultants 6/10/82 NRC-06-77-061 State of Michigan 6/10/82 NRC-01-77-lll Franklin Institute 6/9/82 NRC-04-78-221 Iowa State University 6/9/82 AT(49-24)-0158 University of Virginia 6/4/82 NRC-03-73-037 Corps of Engineers 6/4/82 NRC-02-77-165 Teknekron Research 6/8/82 ADMINISTRATIVE MATTERS Contract No. NRC-02-77-188 with Science Management Corporation (SMC) included a provisional overhead rate and established a ceiling for General & Administrative costs. SMC requested an adjustment to both overhead and G&A as a result of DCAA audit of their records and a subsequent DCAA-directed change to their accounting system. The close out audit of the Contractor's records indicated that they had incurred costs in excess of the contract amount.

Such costs were primarily attributable to actual overhead and G&A rates exceeding those rates established in the contract.

In view of the fact that the ceiling precluded recovery of actual G&A expenditures, the Contractor submitted an alternate indirect rate proposal for NRC'c ccasideration. Based on a review of this proposal and discussions with the DCAA auditor and the Contractor, the Contracting Officer negotiated an adjustment of the overhead rate, made no adjustment to the ceiling on G&A and disallowed $4,565 of the overrun which was not attributable to the difference between actual and provisional indirect rates. The Contracting Officer considered the overhead rate adjustment reasonable since DCAA had directed the changes in SMC's accounting system which resulted in higher indirect rates.

ENCLOSURE A

DIVISION OF SECURITY Items of Interest Week Ending June ll, 1982 Security Liaison Visit 'to ' Senate ' Committee 'on Environment and Public Works, Sub-committee on Nuclear Reaulation SEC personnel met with James R. Curtiss, a Subcommittee staff member, and provided him classified document control assistance and changed the combination to the Com-mittee's NRC-approved security container.

Security Surveys A periodic security survey was conducted of the Natural Resources Defense Council, Washington, DC, on June 9, by Headquarters and Regional Office personnel. A satis-factory security rating will be assigned this classified interest.

An initial security survey of Edlow International, Washington, DC, was conducted on June 10 by SEC personnel who were accompanied by a Region I representative to assess their compliance with 10 CFR Parts 25 and 95, " Access to and Protection of National Security Information and Restricted Data."

Status Report on Vikonics Card Key' System Building

Status of Installation Air Rights III All card readers installed and operating

  • East West (North)

All card readers installed and operating

  • Maryland National All card readers installed and operating
  • East West (South)

All card readers installed but not operating **

Phillips All card readers installed

  • Card readers operating in degraded (stand alone) mode and are not connected to the central processor.

Contractor is scheduled to complete installation and connection of all system components by June 18, 1982. This will involve bringing system on line on a building-by-building basis next week.

    • Lacking AC power which is to be provided by GSA. Attempting to expedite comple-tion of this work by GSA.

Classification Guide SECY-82-211, "NRC Classification Guide for Information Dealing with the Release and Dispersion of Radioactive Material (NRC-RDRM-1)," dated June 1,1982, was for.-

warded to the Commission for review. This guide is classified Confidential Restricted

Data, ENCLOSURE A

OFFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending June ll, 1982 R. E. Ginna Nuclear Power Plant On Thursday, June 3, 1982, members of the NRC' staff and its consultants from Oak Ridge Naticnal Laboratory met with representatives of Rochester Gas & Electric Corporation (RG&E) and Westinghouse to discuss the recent Loose Part Monitor System (LPMS) alarms at Ginna.

Based on the evaluations of the LPMS data, RG&E and Westinghouse have concluded that the alarms are not being caused by a foreign object interacting with the steam generator tubes.

The indications received (a few and widely spaced in time) are not characteristic of a loose part.

The transducer time delays are indicative of noises at or near the shell of the steam generator rather than being generated from within the tube bundle.

By trianculation of the time delays, the Wes'tinghouse analyst was able to establish that the noises were coming from an arc 1 to 4 feet from the feedwater inlet nozzle at an elevation corresponding to the 5th support plate.

There are large mechanical connections (i.e. the support channel between the wrapper and shell and the hydraulic snubbers) in this area.

The licensee postulates that the alarms, which have only been generated at very low (<3".) power levels, are a result of thermal transients experienced by one or more of the components in this area.

The NRC staff and its consultants agree with the licensee that the alarms are most probably not due to foreign objects.

The staff recommended to RGLE that during the intermediate outage planned for 120 EFPD (about Octcber 1982), visual inspections be performed both inside and outside the steam generator in the area where the noises are being generated.

In addition RGLE should analyze the amplitude data of the strip chart recordings in order to make some type of determination of the mass needed to generate the signals received.

RGLE plans to continue to monitor the LPMS closely and procedures have been developed to instruct the operators of the actions to be taken in the event of future alarms.

The Resident Inspector will review the ade:uacy of the procedures.

ENCLOSURE B

No'rth Anna Power Station, Unit No. 2 (NA-2)

NA-2 commenced the 2nd cycle of power operations on June 2,1982. after a 90 day refueling outage.

Actions included in the 1st. refueling outage were: (1) Fuel loading for a 12 month power cycle; (2) Steam Generator Inspection (minor tube denting identified); and (3) Scheduled Inservice Inspection,. Surveillance and maintenance.

Other plant modifications included actions required by NRC licensing conditions, I&E bulletins and TMI NUREG-0737 items. NA-2 will implement a boric-acid bath of the SG's (to prevent further tube denting) prior to power escalations.

CALVERT CLIFFS - Diesel Generator Failures Anincidentoccbrred.onJune3,1982whichresbitedin.thelossofall (three) diesel generators at Calvert Cliffs. With Calvert Cliffs Unit 1 in a refueling outage, Diesel. Generator #11 (Unit 1) was removed from service for maintenance.

In preparation for performing maintenance on a service transformer, the remaining diesel generators (#12 (swing) and

  1. 21 (Unit 2)) were tested. At approximately 5:30 AM, diesel generators
  1. 12 and #21 were shown to be operable. At approximately 6:30 AM #21 diesel generator tripped and #12 diesel generator was started. At approximately 7:00 AM #12 diesel generator tripped and thus all diesel generators were temporarily inoperable.

Calvert Cliffs Unit 2 was operating during this time. At approximately 8:00 AM, diesel generators

  1. ]2 and #21 were declared operable.

The cause of the incident was related to the paralleling of the diesel generators with buses that were being powered from an off-site source.

The licensee is investigating this incident m

ENCLOSURE-B

i a

Bio Rock Point The spent fuel pool expansion hearing began on Monday, June 7,1982 in Boyne Falls, Michigan.

Discussion of contentions is proceeding at a

. slower than expected rate due principally to the extensive cross examination taking place. The delays will affect the hearing schedule since two members of the board need to be in New York next week for the Indian Point hearing.

Consequently, some issues have been " held over" to another hearing session which wo'uld begin around late summer after the Indian Point hearing.

On Monday, the licensee withdrew his structural analysis of the pool because it was considered " incomplete."

It along with several other issues are being held over..The staff informed the board that it expected to complete its review of the licensees response to the 50.54(f)

. letter sent on May 21, 1982 dealing with the affects of loss of pool cooling by June 18, 1982.

North Anna Power Station, Unit No. 1 (NA-1)

NA-1 shutdown on 5/17/82 due to loose parts monitoring signals detected in SG's A&B.

Since then, an inspection of all three SGs has commenced.

A loose object has been found in the hot-leg side of SG-B.

The object has not yet been removed but is thought to be a SG plug.

Some impact damage has been observed on tube sheet and tube ends.

Also, a loose part has been found wedged in a tube at SG-C.

The loose part was detected when attempting an eddy current probe.

The licensee is keeping the staff advised on new information regarding this matter.

Zion Station, Unit No. 1 A meeting will be held with Commenwealth Edison Company on Tuesday, June 15, 1982 at-1:00 p.m. in Room P-422 in the Phillips Building to discuss the licensee's basis for Technical Specifications to assure steam generator tube integrity. The Unit 1 steam generators were recently examined and eddy current indications were found at the anti-vibration bars (AVB) and in the row two U-bends..All of the row one tubes were plugged as were any tubes found to be leaking or with indications which exceeded the plugging criteria.

To assure tube integrity in the event of a main steam-line break, the Technical Specifications limit the amount of primary to secondary coolant leakage.

With the AVB and row two U-bend indications, the current Technical Specification limit is being reassessed.

ENCLOSURE B

I NRR MEETING NOTICES

  • June 11',11982 b

ATTENDEES /

DOCKET l

DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT, NRR CONTACT 6/14/82 50-317 P-110 Discuss the identification and repair Baltimore Gas & Elec.

D. Jaffe l

9:03 am Bethesda of steam generator tube damage at Calvert Cliffs 1 1,

i 6/14-15/82 50-272 Salem Station To review licensees proposed Public Service Elec. & Gas W. Ross i

50-311 Hancocks Bridge, Radiological Efflue ' Technical N.J.

Specifications (Appendix I) 6/15/82 50-382 P-422 To discuss applicant's _QA program Louisiana Power & Light S. Black 9:00 am

-Bethesda (Waterford3) 6/15/82 50-317 Gas & Elec. Bldg. Discuss requirements for resolution Baltimore Gas & Elec.

D. Jaffe 1:30 pm 50-318 Lexington &

of USI A-47 and A-49 for Calvert Liberty Sts.

Cliffs Charles Center Baltimore, Md.

i 6/15/82 50-341 P-110 Discuss proposed changes to the Detroit Edison Co.

L. Kintner

.1:30 pm Bethesda composition of the Femi 2 Safety and Performance Engineering Group l

6/15/82 50-389 P-110 Discuss the following items per-Florida Power & Light V. Nerses 1:00 pm Bethesda taining to St. Lucie 2 Technical i

Specifications: 1) Fomat,

2) Implementation, 3) Changes and
4) Philosophy 9

6/15-16/82 50-447 SE Offices Technical update meeting on General Electric H. Faulkner P

9:00 am Landow Bldg.

GESSAR II PRA

,8 Room 203

'E Bethesda im m

PLEASE BE ADVISED THAT DAILY RECORDINGS CAN BE HEARD ON 492-7166

  • Copies of sumaries of these meetings will be made publicly available and placed in.the respective docket file (s) in the NRC and local public document rooms.

t

NRR MEETING NOTICES

  • s i

I ATTENDEES /

f DATE/ TIME _

NUMBER LOCATION PURPOSE _

APPLICANT;.

NRR CONTACT DOCKET 6/16/82 50-261 Center Plaza Bldg. Discussion of NRC's need for infor-Carolina Power & Light G. Requa

~

1:00 pm Room 3Cl mation for pursuing studies con-(H.B. Robinson 2)

Raleigh, N.C.

cerning USI A-47, Safety Implication of Control Systems, USI A-49, 1

Pressurized Thermal Shock 6/16/82 Holiday Inn Meeting with SEP Owners Group to dis-SEP" Owners Group T. Cheng 9:00 am Bethesda cuss Seismic Equipment Qualification of SEP plants 6/16-17/82 50-537 AR-5033 Discuss the SMBDB Review DOE R. Stark 8:30 am Bethesda 6/17/82 50-341 Detroit Edison Discuss status of items identified Detroit Edison.Co.

L. Kintner 9:00 am 3331 W. Big in the Safety Evaluation Report (Fermi 2)

Beaver Rd.

and its supplements to be verified Troy, Mich.

by NRC staff when completed 6/17/82 50-325 P-118 Discuss forthcoming Fire Protection Carolina Power & Light J. Van Vliet 10:00 am 50-324 Bethesda submittals for Brunswick 1 & 2 6/17/82 50-443 United Engineers Discuss open items related to Public Service Co. of N.H. L. Wheeler l

9:30 am 50-444 Construction, Inc.

applicant responses to MTEB requests (Seabrook) 30 S. 17th St.

for additional information l

i Philadelphia, PA 6/18/82 50-537 Landow 1111 Discussion of Sodium Fire Protection DOE R. Stark g

8:30 am Bethesda for Clinch River P

iO

'E A

PLEASE BE ADVISED THAT DAILY RECORDIEGS CAN BE HEARD ON 492-7166 m

  • Copies of summaries of these meetings will be made publicly available and placed in.the respec the NRC and local public document rooms.

NRR MEETING NOTICES

  • ss DOCKET ATTENDEES /

DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT.

NRR CONTACT 6/22/82 50-537 Landow 1111 Discussion of Chapt. 4 Topics for DOE R. Stark 8:30 am Bethesda Clinch River 6/22-23-24/82 50-537 Burns & Roe Off.

Perform a CRBR Seismic and Structural DOE, TVA and R. Stark 8:30 am Oradell, N.J.

Engineering Audit of Calculations Project.Mgmt., Corp.

6/23/82 50-322, 341, GE Offices Continuing discussion of LRG I General. Electric H. Faulkner 9:00 am 358, 373, Landow 203 proposed modifications.to BWR LRG-1 387, 397, Bethesda technical specifications-416 6/23/82 50-537 Landow 1111 Discussion of Fuel Failure Monitoring DOE R. Stark 8:30 am Bethesda System for Clinch River 6/25/82 50-389 St. Lucie 2 Site NRC management preliminary review Florida Power & Light V..Nerses 8:30 am Hutchinson Is.,

meeting with applicant Florida I

1 k

1 58

  1. ?

l*

PLEASE BE ADVISED THAT DAILY RECORDINGS CAN BE HEARD ON 492-7166

  • Copies of sumaries of these meetings will be made publicly available and placed in.the respective docket file (s) in the NRC and local public document rooms.

o I

NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT l

June 5, 1982 - June 12, 1982 t

Plant Status Core Cooling Mode:

Heat transfer from the reactor coolant system (RCS) loops to reactor building ambient.

[

Available Core Cooling M. odes: ^ Decay heat removal (DHR) systems, Mini DHR (MDHR) system.

RCS Pressure Control Mode:

Standby pressure control (SPC) system.

NOTE:

During Reactor Coolant System feed and bleed, pressure will be maintained with a Reactor Coolant Bleed Tank Pump. Automatic back up pressure control will be provided by the standby pressure control system.

Backup Pressure Control Modes:

MDHR and DHR system.

Major Parameters (as of 0500, June 11,1982) (approximate values)

Average Incore Thermocouples:

102 F Maximum Incore Thermocouple:

127*F RCS Loop Temperatures:

A B

Hot Leg 95 F 98 F Cold Leg 84 F 82*F 88 F 85 F Pressure:

73 psig NOTE:

During reactor coolant system feed and bleed, pressure is maintained at approximately 70 psig.

Reactor Building:

Temperature:

70 F Pressure:

-0.3 psig Airborne Radionuclide Concentrations:

3 2.3 E-8 uCi/cc H (sample taken 6/9/82) 85 6.8 E-6 uCi/cc Kr (sample taken 6/9/82).

5.2 E-9 uCi/cc particulates (sample taken 6/10/82)

ENCLOSURE B

l 1.

Effluent and Environmental (Radiological) Information Liquid effluents from the TMI site released to the Susquehanna River after processing, were made within the regulatory limits and in accordance with NRC requirements and City of Lancaster Agreement dated February 27, 1980.

During the period June 4, 1982, through June 10, 1982, the effluents contained no detectable radioactivity at the discharge point although individual effluent sources which originated within Unit 2 contained small amounts of radioact'ivity.

Calculatiohs indicate that less than two-thousandths (0.002) of a curie of tritium and less than two hundred-thousandths (0.00002) of a curie of cesium were discharged.

2.

Environmental Protection Agency (EPA) Environmental Data 3

The EPA measured Kr-85 concentrations (pCi/m ) at several environmental monitoring stations and reported the following results:

April 16, 1982 May 7, 1982 thru thru Location May 7, 1982 May 21, 1982 Goldsboro 30 30 Middletown 29 30 Yorkhaven 30 31 Observation Center 30 31 No radiation above normally occurring background levels was detected in any of the samples collected from the EPA's air and gamma rate networks during the period from June 2, 1982 through June 10, 1982.

3.

NRC Environmental Data Results from NRC monitoring of the environment around the TMI site were as follows:

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

1-131 Cs-137 Sample Period (uCi/cc)

(uCi/cc)

HP-322 June 2, 1982 - June 9, 1982

<6.5 E-14 < 6.5 E-14 ENCLOSURE B

~ 4.

Licensee Radioactive Material and Radwaste Shipment On Friday, June 11,1982, two Unit 1 liners containing solidified evaporator bottoms were shipped to U.S. Ecology, Richland, Washington.

i Major Activities 1.

Submerged Demineralizer System (SDS).

Processing of the second batch of reactor coolant water (approximately 50,000 gallons) commenced on j

June 5, 1982. On June 8, 1982, processing'was interrupted for an eight I

hour period to replace a process train filter' which reached the ~

differential pressure change out criteria during processing.

SDS i

performance parameters for this batch will be included in the Wet.Kly Status Report following completion of the batch.

2.

EPICOR II. The EPICOR II system is shutdown because no water is ready for processing.

3.

Reactor Coolant System (RCS) Feed and Bleed.

Prior to the next feed and bleed cycle, the rest of the water on the floor of the reactor building (approximately 5,000 gallons) is scheduled to be pumped to the SDS feed tanks in the Unit 2 fuel handling building.

These tanks presently contain approximately 40,000 gallons of water previously pumped from the reactor building.

Attachment I shows weekly RCS samples taken before and after each of the two completed feed and bleed cycles.

Cs-137 was reduced by a factor of 2.3 during the first cycle and by a factor of 1.8 during the second cycle. These numbers closely agree with the expected reduction of a factor of 1.9 assuming perfect mixing during the feed and bleed evaluation.

Sr-90 was reduced by a factor of 1.7 during the first cycle and stayed the same during the second cycle. This was not unexpected because Sr-90 is theorized to be in equilibrium between two forms (soluble and insoluble) in the RCS.

Since the insoluble form is not readily mobile, the feed and bleed only removes the soluble form.

Removal of the soluble form may upset the equilibrium, and over a period of time the insoluble Sr-90 may change to the soluble form until chemical equilibrium is reestablished.

Sb-125 and Co-60 are not expected to be removed by the process and the concentration of these isotopes in samples is usually mcsked by Cs-137. As the Cs-137 is removed, the Sb-125 and Co-60 will become detectable.

The turbidity of the RCS has been reduced by approximately a factor of two during the two bleed and feed cycles.

Further reduction is expected to be small since the turbidity of the feed into the P,CS is approximately 12 NTU because of oxygen absorption.

4.

Reactor Building Entry. During the reactor building entry on Thursday, June 10, 1982, the in-containment nitrogen system was tested and found to be operable. The nitrogen system will be used to inert the primary system components when the reactor coolant water level is lowered in preparation for the control rod drive lead screw removal and closed ENCLOSURE B

{

l J t

circuit television inspection of the reactor vessel upper internals.

lhe next reactor building entry is scheduled for Thursday, June 17, 1982.

Tasks.during this entry will include:

Radiation survey, 1

Installation of an electrical distribution system on the 347 ft.

l elevation, Installation of additional lights in th,e reactor vessel head area, Staging of lead blanket radiation shields, Fire extinguisher periodic survey, and Identify locations on the 305 ft. elevation from where flush water could be directed to the 282 ft. elevation surfaces.

The licensee has installed a coarse filter in series with a fine filter on the inlet to the submerged demineralizer system (SDS) feed tanks.

During the week of June 14, 1982, the licensee is scheduled to pump the remaining water out of the reactor building basement.

The basement pumping operation was previously suspended after the filters to the SDS feed tanks plugged.

It is believed that there may be up to 5,000 gallons I

of water remaining in the reactor building basement.

After the pumping is complete, the licensee plans to flush debris (scheduled during entry on June 21,1982) on the 282 ft. elevation floor to the pump suction in the incore instrument trough.

Flushing operations are also planned l

inside the B "D-ring" where high radiation readings (30 R/hr) were l

detected during an entry on May 26, 1982.

The licensee plans to add enough water during the flushes to cover the sludge on the basement floor with a layer of water.

5.

EPICOR II Prefilter Inerting Tool Status.

The functional test on the EPICOR 11 gas inerting tool was completed this week.

This demonstration test, which integrated the support facility and hardware with the inerting tool, was performed on a cold (non-radioactive) 4' x 4' EPICOR II liner.

The demonstration included a hydrogen enriched environment to simulate conditions in an actual EPICOR II prefilter waste liner. Actually inerting of the first EPICOR liner (PF-3) is scheduled for July,1982.

ENCLOSURE B

t ATTACHMENT I s

RCS WEEKLY SAMPLES.

i i

Date Time Cs-137 (uc/ml) Sr.-90 (u~c/ml)

Sb-125 (uc/ml)

Co-60 (uc/ml) Turbidity (NTU)*

l 5/10 1000 14 18

<2.8 x 10-3 5/17 1300 13 16

<8.4 x 10-2

<2.8 x 10-3 Feed and bleed 5/17/82 - 5/20/82 5/24 1000 5.9 10

<5.5 x 10-2

<3.9 x 10-3 6/1 1030 7.6 11

<1.0 x 10-I

<8.0 x 10-3 Feed and bleed 6/1/82 - 6/4/82 1.8 x 10-3 14 6/7 0900 4.2 11

<2.4 x 10-2 ONephelometric Turbidity Units - An empirical measure of turbidity based on measurement of the light-scattering characteristics (Tyndall effect) of the particulate matter in the sample.

ENCLOSURE B

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OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Weak Ending June 11,-1982 Transfer of Docket Files Pertaining to Regionalization Transfer of the original docket files pertaining to licensing authority dele-gated to Region I by memorandum (from W. J. Dircks, EDO, dated 5/13/82) will take place Monday, June 14, 1982. A preliminary shipment of four boxes was sent June 3,1982, at the request of the region for training purposes. More than 100 boxes are currently being packed for shipment.

Duplicate docket files, maintained by the region, must be forwarded to headquarters within 10 days following receipt of the original files. The duplicates will be kept at headquarters for a minimum of one year.

Planning is underway for their ultimate handling / disposition.

CRBR Fuel Cycle Environmental Review The amendment XIV to DOE's CRBR Environmental Report has not yet been received.

It was scheduled for receipt by May 24, 1982.

Two BPNL key personnel met with NMSS staff to assist in resolving the comments received on the initial draft EIS material.

The majority of the problems have been resolved and it is expected that the NMSS contribution to the updated CRBR FES will be completed on schedule to meet the June 11, 1982 commitment to the CRBR Project Office.

In addition, Discovery Items requiring input from NMSS were received by ELD on June 4, 1982.

All comments must be returned to ELD by COB June 14, 1982.

Concurrently, the NMSS staff is responding to the recent CRBR Project Office request to review Chapter 11 of the original FES (Discussion of Comments).

It is anticipated that both of these items will be forwarded to CRBR-P0 during the week of June 14, 1982.

The next major milestone will be the transmittal of NMSS inputs to the FES including Appendix D, Appendix E and various actions of the FES update to CRBR Project Office by June 11', 1982.

Amersham Corporation Files a Radiological Contingency Plan Amersham Corporation of Arlington Heights, Illinois, has filed a Radiological Contingency Plan.

Amersham earlier satisfied the requirements of an Order signed February 11, 1981, relative to radiological contingency planning by reducing their possession limits below threshold levels specified in the Order.

Amersham now requests that their Plan be incorporated into their license and their possession limits be returned to their former levels.

ENCLOSURE C

1 2

IAEA Advisory Group Meeting l

On June 1-4, 1982, Dr. E. Y. Shum attended the IAEA meeting at Vienna, Austria as a member of the Advisory Group on "Models and Radiological Basis for Recom-mendation on Radionuclide Releases of Regional and World-Wide Interest." At the meeting, a working draft entitled "Radiologica,1 Considerations for Nuclides Dispersec' on the Regional and Global Scale" by K. F. Eckerman and G. N. Kelly

~

was reviewed and discussed.

The Advisory Group also made recommendations to the IAEA on the preparation of a future Safety Series Document regarding the control of radionuclides which may be dispersed beyond national boundaries.

Low Level Waste Storage-TVA_

The Staff has issued its Environmental Impact Appraisal and Safety Evaluation Report on TVA's application to store onsite low level radioactive wasts (LLRW) generated at its Browns Ferry Nuclear Plant.

TVA's application requested authorization to store up to five-years LLRW in reinforced concrete storage modules at the Browns Ferry site but apart from the reactor complex. The application was ori.ginally made as requests to amend the Facility Operating Licenses.

However, in accordance with the provisions of a letter to utilities dated November 10,1981 (generic letter 81-38), for administrative convenience the application was reviewed under the provisions of 10 CFR Part 30. The EIA and SER support the issuance of a separate Materials License.

US/IAEA Safeguards Agreement Members of the Material Transfer SG Licensing Branch (SGMT) met this week with International Atomic Energy Agency (IAEA) staff to discuss the development and implementation of Facility Attachments for the two licensed nuclear facilities recently selected by the IAEA for the application of international safeguards.

Also discussed were some problems associated with the U.S. reporting of nuclear material information to the IAEA.

Problems were identified during the recent physical inventory at the Exxon Facility in Richland, Washington, that appear to be caused by two main problems:

(1) the IAEA computer system does not process corrections to existing data with the same logic under which they are generated; and (2) there are data problems and processing inconsistencies in the nuclear materials management and safeguards system at Oak Ridge.

HMSS ctoff will meet with Exxon and UCC staff in Oak Ridge (June 15-17) to reuncile the Exxon physical inventory with the IAEA and NMMSS book records and to initiate corrective action.

Safeguards Reform for Independent Spent Fuel Storage Installation Recent studies have indicated that it may be exceptionally difficult to sabotage an independent spent fuel storage installation.

A generic issue paper has been developed as part of an effort to reform the physical security require-ments for ISFSIs and reduce unnecessary regulatory burdens.

ENCLOSURE C

NMSS MEETING NOTICES June 11. 1982 Division of Waste Management _

ATTENDEES /

DOCKET DATE/ TIME NUMBER LOCATION PURPOSE _

APPLICANT NRC CONTACT June 15, 1982 Rosslyn, VA US Ecology's Demonstration of Ken Jackson, Lynn Bowser, K. Jackson, i

Computerized Record Keeping Jim Shaffner, WMLL WMLL System June 18, 1982 Willste Building, Briefing by L. Dressen, Chem-WMLL Staff; WMUR Staff; P. Lohaus, 9:00 a.m.

4th Floor Conf.

Nuclear on Activities in State Programs WMLL Room Colorado on Establishment of New Disposal Facility 6

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t.' MSS MEETIf1G NOTICES June 11,1982 s

Division of Fuel Cycle and Material Safety Page 2 6l ATTENDEES /

t DOCKET APPLICANT NRC CONTACT DATE/ TIME NUMBER _

LOCATION PURPOSE

  • June 17 N/A Willste Meet with GNS Company for Nuclear C. E. MacDonald (FC)

C. E. MacDonald Room 517 Services, Ltd.

Pre application C. Marotta (FC) meeting for cast modular iron J. Weidenhammer (RES) shipping cask.

Jack Rollins (GNS)

Rep. from LLL i

i June 21 40-2061

. Chicago, To attend information meeting on-R. E. Cunningham (FC) W. T. Crow k

1 7:30pm Illinois DES relating to Kerr-McGee.

R. G. Page (FC)

W. T. Crow (FC) i W. A. Nixon (FC)

'R. Fonner (ELD)

P. Bollwerk (0GC)

June 21-23 70-698 Oak Ridge, To discuss and resolve internal E. Y. Shum (FC)

E. Y. Shum 70-734 Tennessee comments on EIA covering the Westinghouse Waltz Mill and l

General Atomic license renewal i

action.

June 21-24 Pro,ect Knoxville, '

Presentations on Equipment design W. Birch (0RNL)

W. Burkhardt and testing for advanced fuel C. Bastin (DOE)

M-29 Oak Ridge, Tennessee reprocessing.

W. Burkhardt (FC)

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Juns 11, 1982 HMSS MEETING NOTICES _

Division of Fuel Cycle and Material Safety ATTENDEES /

DOCKET APPLICANT NRC CONTACT _

DATE/ TIME NUMBER _

LOCATION PURPOSE

/

June 13 N/A Miami, Florida To speak to SNM's Legislative W.J. Walker (FC)

W. J. Walker Comittee in reference to Proposed SNM Legislative revision of 10 CFR Part 35.

Comittee members i

i June 14-16. N/A Albuquerque, To work with Sandia Lab on the D. Chapell (FC)

D. Chapell New Mexico Material Licensing Study.

J. Cook (FC) l Rep. from IEAL Rep. from Sandia June 14 70-2946 Willste To discuss storage only license B. Serini (FC)

B. Serini 7:30am Room 555 for Waterford Unit 3 at G. Bidinger (FC)

Louisiana Power & Light Company.

G. Constable (SRI) l l

Travel 50-$01 West Valley, To observe and consult with Rockwell R. Smith (Rockwell)

A. T. Clark postponed New York Hanford on High Level Waste Tank R. Steins.(00E) from 6/7 Inspection at West Valley.

A. T. Clark (FC) to 6/14 June 16-18 N/A' Mia.mi, Flor,ida To speak at Annual Meeting on ALARA R. E. Cunningham (FC) R. E. Cunningham' in the context of.' nuclear medicine SNM Legislative and discuss how an ALARA program Comittee members can be organized in a nuclear I

medicine facility.

June 17-18 70-938 Boston, MA To accompany Region I on.a routine B. Kosla (FC)

8. Kosla inspection of the facility. (MIT)

J. Roth (Region I)

J Meet with Coalition with the Consumer W. T. Crow (FC)

W. T. Crow June 17 70-820 Wood River ~

7:30pm Junctions RI.

Justice to discuss the decomissioning of United Nucle'ar Corporation at the Wood River Junct1,on facility.

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Juna 11,1982 m4SS MEETING ff0TICES Division of Safeguards ATTEtiDEES/

DOCKET t NRC C0f(TACT iTE/ TIME tiUMBER LOCATION

' PURPOSE APPLICANT June 15-17 K-25, Oak Ridge, TN Reconcile inventory data for Gene Sparks, NRC E. Sparks Exxon Fuel Fabrication Facility.

Phil Robinsen, NRC IAEA, NMMSS and Exxon data will Marvin Schnaible, Exxon be compared.

Gerry Doyle, UCCND John Stephens, UCCND June 15 D.C.

Physical Protection of Sea Bob Burnett, NRC R. Burnett Shipments of SSNM Ted Sherr, NRC 10a.m.-lp.m.

Michael McDonough, DOE June 22 State Department Monthly Steering Group Meeting Representatives T. Sherr (TSCC) on Technical Assistance State, ACDA, DOE,

'>a. m. --

NMSS - T. Sherr/

to IAEA L. Wirfs June 15 State Dept.

Action Plan Working Group NRC/NMSS, K. Sanders F a.m.

Meet.ing NRC/IP, State, ACDA, DOE (Tentative)

June 15-18 Willste Bldg.

PNL Contract Reviews NRC/NMSS**

T. Sherr (design features; technical PNL (N. Harms, L. Wirfs objectives follow-on; and C.Bennett, F. Morris, export licensing review P.Reardon1 procedures)

June 8, 9,1982 Willste Bld.

Meeting with Dak Ridge National R.D. Hurt, NRC R. Hurt Lab to discuss Generic Safeguards S.J. Hurrell, ORNL Issues for Reprocessing H.T: Kerr, ORNL 9

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0FFICE OF INSPECTION AND ENFORCEMENT Items of Interest Week'Ending June 11,.1982 1.

The following Significa'nt Enforcement Actions were taken during the past week:

~

a.

EN-82-17, Portland General Electric Company (Trojan) - A Notice of Violation and a Notice of Proposed. Imposition of Civil Penalty in the amount of $60,000 were issued on June 3, 1982. The action is based on one violation concerning failure to complete corrective action on an identified deficiency 1which would, under certain conditions, render one emergency diesel inoperable.

b.

EN-82-18, Overhoff and Associates, Inc. (Cincinnati, Ohio) - A Notice of Violation and a Notice of Proposed Imposition of Civil Penalties in the amount of $500 were issued on June 8,1982. This action is based on unauthorized distributions and transfers of gauges containing licensed material.

2.

The following Preliminary Notifica~tions were dispatched during the past week':

a.

PN0-I-82-40A, Boston Edisnn Company (Pilgrim) - Stuck Traversing In-Core Probe' (TIP) - High Local Radiation In Reactor Building.

b.

PNO-I-82-41, Power Authority of the State of New York (Indian Point Unit 3) -

Federal Emergency Management Agency Report On March 3,1982 Exercise At Indian Point.

c.

PNS-I-82-04, Power Authority Of The State Of New York (Fitzpatrick) - Handguns Undetected During Vehicle Search.

d.

PNO-II-82-61 A, Carolina Power and Light Comoany (Brunswick Units 1 and 2) -

Update On Licensee Report Of Potential Sabotage, e.

PN0-II-82-62, Florida Power and Light Compa'.sy (Turkey Point Units 3 and 4) -

Hurricane Downgraded To Tropical Storm.

f.

PNO-II-82-63, Nuclear Fuel Services, Inc. (Erwin, TN) - Media interest In NFS.

g.

PN0-II-82-64 Virginia Electric and Power Company (North Anna Unit' 1).- Steam Generator Tube Damage.

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PNO-III-82-52, Iowa Electric ~ Light and Power Company (Duane Arnold) - Planned Shutdown In Excess of Two Days Due to Problems On Main Steam Isolation Valve (MSIV).

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PNO-III-82-53, Toledo Edisori Company (Davis-Bessa) - Stuck High Pressure Injection System Check Valves.

j.

PNO-III-82-54, Soils and Materials,, Engineering, Inc. (Livonia, Michigan) -

Damaged Moisture / Density Gauge.

k.

PNS-IV-82-01 and Ol A, Omaha Public Power District (Fort Calhoun Station ) -

Apprehension of Employee With Weapon.

ENCLOSURE D

2-3.

The following IE Information Notices were dispatched during the past week:

a.

IE Information Notice 82-17, Overpressurization Of Reactor Coolant System was distnibuted on June 11, 1982 to all nuclear power reactor facilities holding an operating license or construction permit.

b.

IE Information Notice 82-18, Assessment of ' Intakes of Radioactive Material By Workers was distributed on June ll,1982 to all nuclear power reactor facilities holding an operating license or construction pennit, research and test reactors, fuel facilities, and Priority I material licensees.

4.

Other Items:

a.

Division of Engineering and Quality Assurance 1.

On June 2,1982, representatives from Westinghouse and the NRC met to discuss possible cracking of control rod drive guide tube support pins and the Westinghouse efforts to resolve the issue.

IE is planning to issue an infonnation notice covering this topic in the near future..

ii.

Division staff participated in a meeting on June 8,1982 with. task force members on developing procedures for controlling notifications to the board-on allegations.which are related to investigations by the Office of Investigations.

'b.

Division of Emergency Preparedness The Chief of the Emergency Preparedness Licensing Branch gave a speech on the emergency preparedness appraisal program at the annual ANS conference on June 8, 1982.

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pf * %6 ENCLOSbRE D

IE HEETING HOTICES e.

DOCKET ATTENDEES /

DATE/ TIME _

NUPEER LOCATION PURPOSE APPLICANT NRC CONTACT 6/16/82 50-277/278 Ops Center Operations Center will be NRC Staff B. Weiss l

Bethesda, MD simulated for emergency preparedness exercise.

DEP staff members will be observing at Peach Bottom 6/16/82

,4 ET Room Discussion of criteria and Mr. Jacques Furet B. Grimes state of development of French Commissariat emergency response, a l'Energie Atomique i

6/17/82 Miami, Florida Deliver a speech on enforce-Society of. Nuclear. L. Higginbotha2 ment of the ALARA concept at Medicine Members the Annual Meeting of the f

. Society of Nuclear Medicine 6/18/82,9:00-5:00 Philadelphia,

Discuss the Raychem Report Carfagno and Weiss.

I. Villaiva PA

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Franklin Institute

,Vi /.

6/18/82 ET Room Advise NRC of status of Four-member Korean B. Grimes development of emergency plans delegation and to identify future activities for closer NRC-MOST emergency cooperation.

6/23/82 50-312 '

Ops Center Operations Center will be NRC Staff B. Weiss 8ethesda, MD activated to participate in licensee's emergency preparedness exercise, DEP staff members will be m

M observing at Rancho Seco b

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IE MEETIllG IIOTICES DOCKET ATTENDEES /

DATE/ TIME Nt2EER LOCATION PURPOSE APPLICANT NRC CONTACT 6/24/82 8:30 United Engineers ASME Comittee on Owners Comittee Members J. M. Taylor Center. NY, NY Certification f

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OFFICE OF NUCLEAR REGULATORY RESEARCH Items of Interest Week Ending June 11, 1982 ACRR Debris Coo ~. ability Experiment D-7 Debris coolibility experiment D-7 was performed in the ACRR test reactor on May 28,1982.

This is one in a series of in-pile experiments on the coolability limits of fission-heated particulate core debris in sodium (simulating decay heat) in a joint program with EURATOM and Japan.

The purpose of experiment D-7 was to measure the coolability limits of a relatively thin (7.4 cm) stratified bed of LMFBR particulate debris, and in D-7 measurement, were extended to relatively low sodium sub-cooling (1000C).

Preliminary results on the dry-out coolability limits degree well with the current Lipinski I-D model for stratified packed beds. The experiment was prematurely terminated after 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by failure of the debris-containing double-walled crucible. This was a new crucible design, and the failure mode is easily correctable for f/ture experiments.

Companion experiment D-9, a stratified bed with a large faction of fine debris, is scheduled for July.

l TRAC Analyses T. Lee and N. Zuber from RES and W. Lyon from NRR visited LANL to discuss with Q-7 group the results of their TRAC analyses of the SBLOCA recovery for B&W plants. Many issues have been resolved; however, LANL failed to explain several transient flow phenomena.

LANL will propose shortly th9tr plan to resolve the remaining issues.

3-D Flow Mixing 1

A meeting with T-3 group of.LANL was also held to discuss the numerical scheme and the turbulence model in their analyses of 3-D flow mixing in the cold legs and the downcomer for PTS to PWR's.

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ENCLOSURE E

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JAERI-CRT Program A meeting with Dr. Y. Kukita of JAERI was held June 4,1982 to discuss i

the current status of the JAERI-CRT program.

It was noted that there were no new observations that may have an impact on Generic Issue, Task A-8 which has just been closed.

Research programs related to H9 problem were also discussed with Dr. Kukita indicating that JAERI is considering initiating some H research programs of their own and he was informed where NRC stan$s on the issue to avoid repetitive effort.

FLECHT SEASET

~

Westinghouse successfully ran Test No. 9 (one-phase, two-phase and reflux transient with steam generator secondary side' boiling

to dry out and refill) last week.

I NRC, EPRI, Westinghouse and PNL will conduct a technical meeting on June 17 to determine the flow blockage models that will be utilized in COBRA-TF for the 163 blocked bundle analysis.

Data Bank Data from FEBA (Flow Effects Blockage Apparatus) Test Series 4 were added to the data bank: Run Numbers 4264 and 4267. Also, data from LOFT Tests L6-6A and L6-6B were added to the bank. These LOFT data simulate a boron dilution accident.

LOFT Preparations are continuing on schedule for the next test, L2-5, planned for Wednesday, Jun.e 16, 1982. The test will be a double ended cold leg break at 12 kw/ft, with the reactor coolant pumps stopped early rather than allowed to coast down normally. The ACRS ECCS subcomittee, which will be meeting in Idaho Falls the. day of the test, is planning to witness the test.

The L2-5 test will provide intennediate infonnation between the L2-3 test, unpressurized rods, and the L2-6 test, high pressure rods. Next week's test is not expected to result in fuel damage.

ENCLOSURE E

hl 1

Semiscale

~

A 50 percent steam line ' break test was run on Semiscale last week.

The test indicated that this size break is a rather benign transient for the reactor coolant system. Since a smaller steam line break will be more benign, the Semiscale program has been reevaluated and the planned 2.5 percent steam line break test has been dropped.

Preparations are now underway to run.the S-07-6 repeat test by late June 1982. One week after that test a primary side feed and bleed test will be run.

Due to its susceptibility to small effects, each time a primary feed and bleed test has been attempted as an add-on test, primary system pump leakage, a small effect, has prevented obtaining acceptable results.

Therefore, following the 5-07-6 repeat the pump will be replaced with This course the spool piece used in the natural circulation tests.

of action was decided upon as the.way in which the NRR needs for feed and bleed data could be satisfied.

Testimony Given in Workman's Compensation Trial in Canton, Ohio - June 3-4, 1982 On June 3-4, Harold Peterson of the Division of Health, Siting, and Waste Management, RES, testified in a workman's compensation trial in Canton, Ohio at the invitation of the Stark County Prosecutor's office. Mr. Peterson testified as to the radiation levels around the Three Mile Island site following the March 28, 1979 accident.

A county employee who was in the TMI area on April 5-6, 1979 filed a workman's compensation claim for alleged radiation effects as a result of being near the Three Mile Island site.

ENCLOSURE E

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RES MEETIriG fiOTICES_

ATTENDEES /

DOCKET APPLICANT NRC CONTACT DATE/ TIME _

tiUMBER_

LOCATI0ti PURPOSE (If Applicable)

Helsinki, Finland Enlarged Halden Program M. Silberberg/

M. Silberberg 6/14-18 Group Meeting (Halden Halden Program Invitation)

Group 6/21 St'ockholm, Sweden Meet with Marviken Management Marviken Mngt/

. M. Silberberg on Proposed Marviken Tests M. Silberberg 6/23-2S Albuquerque, NM NRC/EPRI Review on Marviken EPRI/NRC/Sandia/

R. R. Sherry Proposal BCL/0RNL M. Silberberg TSdetermineflowblockage Richard Lee Richard L_ee June 17 Denver, C0 models Y. Y. Hsu 8:00 June 16 Idaho Falls, ID L0fi L2-5 Test Ralph Landry Ralph La'ndry Harold Sullivan June 16-17 Idaho Falls. '

ACRS'ECCS e ting Harold Sullivan Harold Sullivan R

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June 11.1997 RES MEETING NOTICES _

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ATTENDEES /

1 APPLICANT NRC CONTACT _

DOCKET PURPOSE DATE/ TIME NUMBER LOCATI0t{

l l

(If Applicable)

LSTong, RES Attend workshop on Novel Oak Ridge, Tennessee

/14-15 Design Concepts for Light Water Reactors Dross /R8Hinogue ORNL Research program management Dak Ridge, Tennessee 5/28-29 review.

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E. Hawkins L. Brown Symposium on LLW Disposal:

T. Nicholson Arlington Hyatt Site Characterization and T. Schmitt f16-17 Monitoring E. Zurflueh R. Kraus To conduct a critical Cognizant NRC staff C. Jup' iter contractors, and Counsel. Room se 14-16 technical review of Sheraton Inn consultants 8727 Colesville Rd the hydrological and Silver Spring, MD geet:hemical modeling aspects of the RES waste management research 9

program.

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. June 11,1982 RES MEETING NOTICES _

ATTENDEES /

DOCKET APPLICANT NRC CONTACT _

DATE/ TIME _

HUMBER LOCATION PURPOSE (If Applicable)

UKAEA-USNRC Research Coordinators R. Minogue/

R. Minogue Culcheth,UK Jose Cortez June 15,1982 Meeting Discuss fuel-related work and R. Minogue/ Jose Cortez/

R.itinogue June 16, 1982 Springfields, UK

0. E. Bassett Springfields Nuclear tour facility Power Development Laboratories June 17,1982 Bournemouth, UK Discuss LOCA topics and tour R. Minogue/ Jose Cortez/

R. Minogue O. E. Bassett UKAEA Atomic Energy facility Establishment Discuss radiological protection R. Minogue R. Minogue June 18, 1982 London, UK standards and applications of llealth & Safety rish assessment to the " inquiry".

Executive Nuclear Installations

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7 June 11,1982 RES MEETING NOTICES ATTENDEES /

DOCKET APPLICANT _

NRC CONTACT _

DATE/ TIME NUMBER LOCATION PURPOSE (If Applicable)

J. Jones PUBLIC MEETINGS ON THE ADVANCE NOTICE OF PROPOSED RULEMAKING ON CERTIFICATION OF IN June 8, 1982 Atlanta, Georgia 9:00 am Colony Square Hotel June 10,1982 Houston, Texas 9:00 am University of Texas School of Public Health Auditorium June 15,1982 Oakland, California 8

Hyatt Oakland Hotel' 9:00 am June 17,1982 Chicago, Illinois 9:00 am Americana Congress Hotel June 23,1982 Washington, DC 9:00 am GSA Auditorium Room'2318 RH08 Bouguard Hearing June 15, 1982 1:00 pm June 16-18,1982 Paris, France CSNI Senior Group of P.5==M4y D. Ross R. Minogue Experts on Severe Accidents v

Interagency Committee Committee members E. Oklesson NBS

(' June 16,1982 Gaithersburg, MD on Standards Policy 10:00 am v

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l June 11,l_982 RES MEETING NOTICES

!l ATTENDEES /

DOCKET APPLICANT _

NRC CONTACT _

DATE/ TIME _

NUMBER LOCATION _

PURPOSE _

(If Applicable)

June 12-18 Miami Beach

  • Society of Nuclear Medicine Deborah A. Bozik Annual Meeting
  • Attendee is going for the following reasons:

(1) To take part in,a Discussion / Commentary of which she will discuss "Guidelinesafor Patients at Home following Treatment with Radioiodine*

There has been press interest in this topic.

(2) To respond to an invitation from the SNM's Committee on Government Relations to discuss the proposed revision to Part 35, (3) To respond to an invitation f rom 'the SNM's Publications Committee to b s-M E

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June 11, 1982' RES MEETING NOTICES ATTENDEES /

DOCKET APPLICANT NRC CONTACT DATE/ TIME NUMBER LOCATION PURPOSE (If Applicable)

Fontenay aux Roses, Review NRC-CEA ongoing Cortez/Bassett R. Minogue 6/21/82 cooperative activities Paris Centre D' Etudes Visit laboratory 6/22/82 Nucleaires De Grenoble Cadarache Labs visit labs 6/23-24/82 J. Cortez 6/25/82 Ispra, Italy Visit ESSOR Facility &

update NRC/JRC Cooperation 6/15/82 Bal timore Gas &

Design info acquisition on R. J. Mattson R. J. Mat,tson,NRR Electric Calvert Cliffs for NSI A-47 E. C. Wenzinger Bal timore, MD and A-49 D. Basdekas ORNL BG&E 6/16/82 Carolina Power & Light Design info acquisition on R. J. Mattson R. J. Mattson,NRR Raleigh, North Carolina H. B. Robinson'ror NSI A-47 E. C. Wenzinger and A-49.

D. Basdekas ORNL CP&L 6/28/82 Institute for Nuclear INP0/RES interface meeting Mr. Zebroski,INF0 R. B. Hinogue Power Operations Minogue/ Goll.er, RES y

Atlanta, Georgia G8

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ITEMS OF INTEREST 0FFICE OF INTERNATIONAL PROGRAMS WEEK ENDING JUNE 11, 1982 IAEA and NEA Travel Mr. Ronald Hauber, IP, attended the June 7-10 IAEA Board of Governors meeting in Vienna, Austria.

On Friday, June ll, Mr. Hauber will meet with officials of the Nuclear Energy Agency at the OECD Headquarters in Paris, France, and on June 14 will go to Spain to discuss organizational changes and information exchange activities.

Technical Cooperation NRC has received a request from the Mexican National Nuclear Safety and Safe-guards Commission (CNSNS) for assistance in nominating a candidate to fill a one-year IAEA advisory position in Mexico.

The CNSNS is looking for a candidate with experience in the preoperational stage to assist in the transition from the construction phase to the operation phase at the Laguna Verde nuclear power facility.

The CNSNS would also like to discuss with NRC a proposal to set up three sequential 4-month assignments of CNSNS engineers at a U.S. BWR in the preoperational stage.

Foreign Visit to NRC On Monday Mr. Raymond Klersy and Mr. Helmut Holtbecker of the Joint Research Centre in Ispra, Italy met with Commissioner Roberts, J. Lafleur, Jr., IP, and R. B. Minogue, D. F. Ross and C. Kelber of RES to discuss research projects of mutual interest.

Arrangement / Agreement Activity The Executive Branch this week provided its clearance for NRC to proceed with the proposed " Arrangement Between the USNRC and the Commission of the EC on Behalf of Euratom on In Pile Light Water Reactor Loss of Coolant Accident Simulation." We still await the EC's comments on the redraft passed to F. LaFontaine of the EC's Washington delegation on May 18.

IP has drafted and is circulating for ELD and RES review a proposal which would open the research program entitled " Determination of Long-Term, Low Temperature LWR Rod and Crud Behavior During Dry Storage" to international participation.

NRR's CRBR Program Office has asked IP to collect all available information on steam generator tube leakage at sodium-cooled reactors, including the type i

of material used in the SG. We are cabling our Arrangement Administrators in l

France, the UK, Japan, and the FRG with this request and asking the Science Counselor in Moscow to obtain Soviet experience if possible.

ENCLOSURE G L

I 2

Retransfer from France to Japan IP has received for advance review a partiil DOE analysis of a proposed transfer of 105 kilograms of plutonium recovered at.La Hague from Japanese spent fuel of U.S. origin. This would be the first transfer of separated plutonium outside of EURATOM since passage of the NNPA of 1978.

The staff will prepare its own analysis of this request upon receipt of additional information concerning the physical security arrangements involved.

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ENCLOSURE G

Foreign Reports l

l Deleted from PDR copy Indicates the reports are in English ENCLOSURE G

I

,o 0FFICE OF STATE PROGRAMS ITEMS OF INTEREST WEEK ENDING JUNE 11, 1982 Review - South Carolina Radiation Control Program The South Carolina radiation control program will.be reviewed the week of June 14, 1982.

Transportation of Radioactive Material in Michigan The Michigan Department of Health, under a joint NRC/U. S. Department of Transportation contract conducted their fourth year-study-for the period September 1, 1980 through August 31, 1981 to assess the transport of radioactive materials in Michigan.

" Transportation of Radioactive Material in Michigan," was issued as NUREG/CR-2736. Major findings include the following:

o most radioactive material transported into and through Michigan is comprised of radio-pharmaceuticals; o investigations revealed that minor violations of packaging and shipping paper regulations persist but to a lesser degree than in previous years; major operations pr'obleIns associated with two courier o

companies have substantially improved but still require improvement; and o joint investigations with Federal agencies were made, and some resulted in legal action on shippers.

Status Report:

Low-level Radioactive Waste Compacts The NRC reviewed and commented on the 00E draft " Status Report: Low Level Radioactive Waste Compacts," in a letter dated June 11, 1982 to Mr. Franklin Coffman, Acting Director, Office of Terminal Waste-Disposal and Remedial Action, Office of Nuclear Energy. Major concerns include:

o having new operating sites by 1986; o appropriate makeup of compacts; and o clarification of Congressional intent with regard to other Jederal government activities than.those of the U. S. Department of Energy and Federal.

research and development.

ENCLOSURE H

Junn 11, 1982 SP MEETING NOTICES I

DATE LOCATION PURPOSE ATTENDEES / APPLICANT NRC CONTACT June 14-Lexington, Va.

Meeting of Uranium Sub-Committee Members R. Scarano committee of Va. Coal and and Invitees 15, 1982 Energy Commission on Uranium Regulation l

O 771 58 Mi x

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i REGION'I I_TEMS OF INTEREST WEEK ENDING JUNE 11, 1982 Pilgrim Nuclear Power Station Alert An Alert was declared at Pilgrim at 3:20 p.m. on June 3,1982, when a Traversing In-Core Probe (TIP) retracted beyond its normal shield chamber due to a limit switch failure. The Region 'I Incident RE;-

sponse Center was placed on standby at 3:50 p.m.

The Station Emer-gency Plan specifies that an Alert be declared if radiation leYels in an accessible area of the plant increase by greater than a fac-tor of 1000 in one hour.

Radiation levels were 50 to 90 Rem /hr on contact with the TIP machine and 2 Rem /hr general area. There were r.o overexposures to personnel or airborne radioactivity releases.

The Alert was terminated at 5:11 p.m., based on decreasing radiation level s.

Repairs are underway.

The plant remains in operation.

Resident and Regional Inspectors wene onsite throughout the event end followed licensee actions.

Salem Nuclear Generatino Station Strike Update Both units continued to operate throughout the week at or near full pcxcr with no significant problems.

A tentative contract agreement was reached with the striking IBEW on June 7,1982, and ratified by the members on June 10, 1982.

The contract represents a 20.6% in-crease in total benefits over two years as compared to the company's offer before the strike of 18.5%.

Union members started to return i

to work at 12:01 a.m. June 11, 1982, ending the 41 day strike.

Re-turning licensed operators will be phased back into licensed duties within 3 shifts, after participating in a refresher training pro-gram. Other workers (Maintenance and Instrumentation / Control Technicians) will receive reorientation training before actually working in the plant.

The licensee implemented a special, post-strike security program when the strikers started to return to work.

This program will remain in effect until the licensee and Region I are satisfied that no workers are harboring hostilities to-ward the company.

Twenty-four hour NRC inspection coverade also will continue to monitor worker attitude and work practices.

Two physical protection inspectors were dispatched to the site to assist in this coverage.

Initial reports from NRC inspectors onsite indicate that the werkers appear enthusiastic about returning to work.

ENCLOSURE L

REGION I MEETING fiOTICES June 11. 1982 DATE DOCKET ATTENDEES /

DATE/ TIME HUMBER LOCATION _

PURPOSE APPLICANT NRC CONTACT June 17,1982 50-387 &

Susquehanna Site, SALP Presentation to R. Haynes and staff; E. McCabe 10:00 a.m.

50-388 Berwick, Pa.

Licensee licensee site ard cor-porate managers.

Juna 16, 1982 50-387 &

Benvick, Pa.

Meeting with Berwick:

R. Haynes and stiff; E. McCabe 7:30 p.m.

50-383 Pa. area local offt-Berwick, Pa. Hay >r and cials council members.

~

Arlington, VA Symposium on Low-Level State Officials Faith N. Brenneman 6/16-17 8:00 AM h'aste Disposal; Site Characterization and Monitoring ORNL/NRC King of Prussia, Region I State Liaison State Officials Faith N. Brenneman 6/24-25 PA Officers' Meeting O

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REGION III MEETIEC NOTICES June 11, 1982 ATTENDEES /

DOCKET DATE/ TIME ffJ MER LOCATION PURPOSE APPLICAtIT NRC CONTACT C*

June 17, 1982 9 a.m.30-305 Kevaunec, WI Systematic Appraisal of Wisconsin Public T.N.Tambling Licensee Performance Service Corp Kevaunee Kucicar Plant Region III staf f June 16,1982 Kansas City. 10 Shared responsibilities FEMA Regional Director 10: 30 a.m.

during energencies J.G. Keppler 6 staff J. G. Keppler June 18, 1982 50-440 Glen Ellyn, IL Region III investigation Clevelar.d Electric 10:00 a.r..30-441 results Illuminating J.G. Keppler 6 staff June 21, 1982 50-239 Systematic Appraisal of Consumers Power 1:00 50-330 Jackson. IG Licensee Performance Region III Staff T.N. Tambling tudiand Nuclear Plant June 22, 1982 50-373 Washington, D.C.

BricEing on LaSalle NRC Conmissionera 50-374 Investigation J.G. Keppler & staff J. G. Keppler Argonne IL Contract Licensing A.B. Davis Jun., 23, 1982

~

Assistance A. B. Davis 9:00 a.m.

Jur.e 23, 1982 50-266 Glen Ellyn, IL rnforcenent Conference Wisconsin Elec. Co.

1:00 p.m.

50-301 J.G. Keppler & staff 9

50-266 Glen Ellyn, IL Systematic Appraisal of Wiscensin Elec. Co.

3:00 p.m.

50-301 Licensee Performamce J.C. Keppler 6 ntaf f T.N. Tambling m

r-CA Reported in previous weekly report.

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I REGION V ITEMS OF INTEREST WEEK ENDING JUNE 11, 1982 i

Portland General Electric Company Trojan - DN 50-344 Underwater TV inspection of the bottom of the reactor vessel has ' revealed t e presence of 2 or 3 fuel pellets and a piece of steel sheet about 7" x 15" x!!/8" thick with torn edges.

In order to remove these items, the licensee plans to rer.ove the core barrel, and expects to perform this operation on Monday, 6/14/82.

It has been speculated that the piece of metal may be a portion of a thermal sleeve from somewhere in the system, but a better determination can be made after the piece has been retrieved and examined in greater detail, i

Snuthern California Edison Company Ean Onofre - 1,2,3 - DN 50-206, 50-361, 50-362 cna1nnan Pa11ad1no and Reg 1onal Adm1n1strator Engelken Vis1ted the San Onofie site on Wednesday, June 9, 1982.

ENCLOSURE L

REGION V f4EETIllG fiOTICES iiEEK ENDING 6/11/82 DATE/ TIME _ ~~ DOCKET NO.-

-~ LOCATION PURPOSE ATTENDEES /

NRC CONTACT APP _LICANT

~

6/15/82 50-397 Region V Discuss Reverification R. Hatlock R. T. Dodds 8:30 a.m.

Prograni 6/15/82 50-528 Region V Discuss QA Audit Prcgram B. Kaplan T. W. Bishop 8:00 a.m.

Region V Discuss ETEC Services A. Onesto T. W. Bishop 6/15/82 1:00 p.m.

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n ITEMS ADDRESSED BY THE COMMISSION - WEEK ENDING JUNE 11, 1982 A.

STAFF REQUIREMENTS - BRIEFING ON ENVIRONMENTAL QUALIFICATION OF ELECTRICAL EQUIPMENT - FINAL RULE (REF. SECY-82-207), 2:00 P.M., TUESDAf, JUNE 1, 1982, COMMISSIONERS' CONFERENCE ROOM, DC 0FFICE (OPEN TO PUBLIC ATTENDANCE), Memo Secy for the Record, 6/10/82 l

The Commission was briefed by staff *on the proposed final i

rule on Environmental Qualification of Safety-Related Electrical Equipment for Nuclear Power Plants.

(Subsequent to the meeting, additional partial guidance on this matter was provided to staff in a SECY memo dated June 10, 1982.

Final guidance will be provided upon Comnission review of SECY-82-207A dated June 9', 1982).

B.

SECY-82-207 - FINAL RULE, " ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRIC EQUIPMENT FOR NUCLEAR POWER PLANTS", Memo Secy to Dircks, 6/10/82 The Commission has asked that it be provided with a draft immediately effective rule that would extend the present deadline of June 30, 1982 for qualification of electric equipment.

The draft should offer the Commission a choice between two alternatives:

(a) an extension for a specific period of time, i.e.,

90 days; and (b) an extension consistent with the deadlines in SECY-82-207, i.e.,

the second refueling beyond March 31, 1982 with provisions for extensions to November 30, 1985.

The rule should also state that all of the other requirements and provisions of CLI-80-21 remain in effect, that present programs of equipment qualification should continue, and that the Commission intends to issue a final rule on equipment qualification requirements in the near future.

Justification of the extension, based upon the adequacy of the submittals to the NRC and the staff's determination that the utilities have justified continued operation, should be included.

(J.DC) (SECY SUSPENSE:

6/18/82)

$2.5 ENCLOSURE 0