ML19248D263
| ML19248D263 | |
| Person / Time | |
|---|---|
| Issue date: | 07/25/1979 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-790725, NUDOCS 7908150468 | |
| Download: ML19248D263 (36) | |
Text
.
t July 25, 1979 For:
The Commissioners From:
T. A. Rehm, Assistant to the Executive Director for Operations
Subject:
WEEKLY IfiFORMATION REPORT - WEEK ENDING JULY 20, 1979 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
Standards Development C
Nuclear Material Safety and Safeguards D
Inspection and Enforcement E
Nuclear Regulatory Research F*
Executive Legal Director G
International Programs H
State Programs I
Management and Program Analysis J
Controller K
Calendar of Significant Events L
Items Approved by the Commission M**
Calendar of Speaking Engagements N
c A. Re m, Assi + n n4h Executive Director for Operations
Contact:
T. A. Rehm 49-27781 gjqgrl}
7908150'(67
- No inout this week
- Deleted from Commissioners and PDR copy
SUM!!ARY OF KEY EVENTS Week Ending July 20, 1979 Salem, Unit 1 In conjunction with the spent fuel pool hearing for Salem, Unit 1, NRR committed to providing a response to ASLB on whether the TMI-2 event is considered to have been a " Class 9" accident.
ASLB may decide to allow testimony from all parties to the Salem proceeding on the potential effects of such hypothetical accidents on the Salem expanded SFP.
Arkansas Nuclear One, Unit 1 (ANO-1)
On July 10 ANO-1 shut down due to excess vibration in the main turbine.
As of July 16, no problem had been found in the turbine.
It is expected that after resetting t' e balance weights, reassembling the turbine and correcting a snubber and hanger problem, the plant will be ready for startup by July 25.
Palo Verde,~ Units 4 & 5 Arizona Public Service Company suspended its plans to build Palo Verde, Units 4 and 5 because continued carticipation by California utilities was impossible in view of questions and objections of the PUC, Energy Commission and Governor Brown.
Uncertainty of the Federal regulatory process was also cited.
H. B. Robinson IE advised Carolina Power & Light Company not to resume operation of Robinson until questions concerning the licensee's base plate anchor bolt problem has been resolved.
Shioments of Spent Fuel The first route approved for shipment of s pent fuel under the new rule, that became effective July 16, was between Hartsville, SC and Southport, NC.
Clearance Rule At the Commission's request, NMSS drafted a new version of the Clearance Rule.
This version excludes nuclear reactors and storage facilities of irradiated reactor from the rule's requirements.
ELD will provide opinion on alternative programs and will forward the draft to the Commission, Report to Congress on Alternative Fuel Cycles N"SS has prepared the safeguards chapter of the NRC Report to Congress on the Status of Domestic and International Evaluations of Nuclear Fuel Cycle Systems as mandated by the Authorization Act of 1979.
The chapter presents an overview of 17 fuel cycles being considered by DOE, the means applicable to each for safeguarding against proliferation, and resulting safeguards considerations.
Udall Hearings IP prepared testimony for Chairman Hendrie to be presented before the Udall Comittee on July 26.
The hearings will deal with nuclear proliferation and NRC's role in implementing the U.S. policy.
L M.VG
. Emergency Preparedness SP prepared a report to the Commission on efforts to accelerate the development of State and local government radiological emergency respcise plans.
The report will be updated and submitted monthly to the EDO.
Information Storage and Retrieval fcr incident Response MPA is exploring advanced image storage and retrieval techniques embodied in videodiscs for possible application to NRC incident response. A task force has been formed to evaluate use of the disc and will present results of their review to the EMT.
Budget Formulation The EDO completed his mark on the FY 1980 budget supplemental and the FY 1981-1933 budget.
ED0 recommendations will go to the Commission July 23, 1979.
b lS??
OFFICE OF ADMINISTRATION Week Ending July 20, 1979 ADMINISTPATION OF THE FREEDOM 0F INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Jnitial Decision Rec?ived 307 20 Granted 164 5
Denied 50 6
Pending 93 9
ACTIONS THIS WEEK Received Barry Scott Requests a copy of a study performed by the NRC on (79-266) the potential hazards to consumers and to the environment from the use and disposal of ionization type smoke detectors.
Kenneth Marek, Requests access to records concerning proposed licens Center for Development to export low-enriched uranium to Brazil, and Policy U.S. involvement in Brazil's nuclear energy programs, (79-267) especially the Angra I project.
Bruce M. f(yman Requests documents relating to the TRIGA auclear (79-268) reactor at Columbia University in New York, and other TRIGA reactors.
June Allen, Referral f rom the Department of Justice of documents North Anna Environmental regarding an investigation of alleged withholding Coalition of information concerning nuclear plants operated (79-269) by VEPC0.
Gary Howard Simpson, Requests documents regarding the FY 79 budget on Attorney-At-Law training and travel for ADM, I&E and RES as of (19-270)
June 15, 1979, and data on promotions in the Office of Administr.ation for FY 79.
Joan McMahan, Requests all correspondence between NRC and the Safe Alternatives Appalachian Power Company or American Electric for Future Energy Power Company referring to nuclear power plants (79-271) to be constructed in the next 15 years in Virginia or West Virginia.
John Raymond, Requests all files in the NRC indexed or maintained Murv Glass, under the name of Karen Silkwood.
Common Ground (79-272) 6MW8 CONTACT:
J. M. Fel ton 492-7211 ENCLOSURE A
2 Received, Cont'd Susan M. Pierce, Requests a copy of the winning technical proposal Attorney-At-Law for RFP 79-134, " Tearing Stability Analyses for (79-273)
Light Water Reactor Piping" and pages 1 through 7 of the RFP.
Michael Burke, Requests records relating to accidents at fiUMEC Valley fiews Dispatch in which employees were exposed to radioactive (79-274) material, and to allegaticas by a Babcock & Wilcox employee concerning dumping of radioactive wastes and plutonium contamination of a restaurant.
John M. Cannon, Requests a copy of the film on the LOFT experiments Mid-America Legal and all supporting documents relating to the content Foundation and production of the film.
(79-275)
Jack R. flewman, Requests copies of four documents cited in a Attorney-At-Law memorandum dated June 11, 1979 from Stephen Eilperin (79-276) to the Commission entitled "D.C. Circuit's Recand in h te of Minnesota v. TIRC."
Granted Dean Hansell, In response to a request for records regarding the State of Illinois decommissioning of the Elk River, Minnesota reactor (79-113) and the shipment of the decommissioned material to the Sheffield, Illinois low-level nuclear waste site, made documents available at Region III in Illinois.
Charles W. Solbrig, In response to a request for a copy of an fiRC comput tiuclear Fuel Services code and system and related documentation, informed (79-169) the requester the WRAP code will be available at a later date, and the JOSHUA system may be obtained by contacting the Savannah River Laboratory.
Jack Grossman, In respons,e to a request for the Stone and Webster Island Closeup News Engineving Company's " Design Coordination Reports,"
Service which relate to construction of the Shoreham (79-196) fluclear Power Station, informed the requester that these are not fiRC records and, therefore, are r ot subject to an FOIA request.
John M. Bryson, Made available 10 documents regarding the promulgati STEPT0E & JOHNS 0fi of 10 CFR Part 140, Appendix A.
(79-224)
E ' M 3 f: 9 ENCLOSURE A
3 Granted, Cont'd Wayne Coffman Made available a copy of the technical proposal (79-225) for RFP-PS-f;RR-79-107.
Michael M. Maney, Made available 10 documents regarding the Sullivan and Cromwell promulgation of 10 CFR Part 140, Appendix A.
(79-226)
Barry Ahrendt, In response to a request for summaries of 3ower WBTV flews plant operator exam results presented to t1e (79-233)
Commission on April 20, and the operator license examinations and test results from January 1,1975 to date for any other Duke Power employees, made available these records.
Daniel C. Ring, In response to a request for records relating to Silver Lake fiews wastewater discharges from the Pilgrim I fiuclear (79-236)
Power Plant, informed the requester that these records are located in the LPDR in Plymouth, Massachusetts.
D. Loggins, Made available the 1978 report on nuclear wastes, (79-241) prepared for the f4RC by the fiational Academy of Sciences.
Lynn Connor, Made available a copy of the fiUREG-0485 revision and Doc-Search Associates update entitled " Regulatory Licensing, Status (79-243)
Report, Systematic Evaluation Program--Draf t Issue (April 20, 1979)."
(An individual requesting Made available documents pertaining to the information about himself) issuance of his operator license.
(79-256)
Denied rione bv3321 f)
Ef4 CLOSURE A
DIVISION OF CONTRACTS Week Ending July 20, 1979 PENDING COMPETITIVE REQUIREMENTS 1.
RFP RS-NMS-80-022 Title - Management Control System for Sealed Source and Device Review Description - Technical assistance to upgrade and improve the present NRC sealed source and device review and cataloging system and to provide for accurate document control, standardized review procedures, and rapid and accurate retrieval of catalogued i n formation.
Period of Performance - Eleven and one-half months Sponsor - Office of Nuclear Material Safety and Safeguards Status - Solicitation being developed 2.
RFP RS-NMS-80-024 Title - Development of An Advanced Material Accounting System Sinulation Model Description - Develop a model which will be used by NRC to evaluate current material accounting practices at licensed nuclear fuel cycle facilities and which will serve as an input for studying advance data analysis techniques.
Period of Performance - One year Sponsor - Office of Nuclear Material Safety and Safeguards Status - Solicitation being developed 3.
RFP RS-NMS-80-027 Title - Environnental Assessment of Surface and Groundwater Impacts from Uranium Recovery Operations Description - The Commission, in its review of license applications, renewals, and modifications requires the technical assistance of a contractor to assist in the development of environmental appraisals and impact statements.
The effort requires a review of applicants' submittals and the preparation of an environmental assessment.
The assessment, along with other data, will be furnished in a technical evaluation report.
The contractor shall additionally be prepared to respond to public comment on these assessments and to possibly collect actual field data on same sites.
Period of Performance - Two years Sponsor - Office of Nuclear Material Safety and Safeguards Status - Solicitation being developed ENCLOSURE A C/@l1 4.
RFP RS-NMS-80-028 Title - Licensing Assistance Enviror. mental Impact Statement Preparation Description This effort requires contractors to support the NRC's licensing r? view process through providing assistance in the preparation of environmental impact statements for these applications.
The work required a review of each licensee's, actual or anticipated, submittal.
Following the review the contractor shall provide a draft environmental impact statement (DEIS) and subsequently a final environmental impact statement (FEIS).
Period of Performance - Three years Sponsor - Office of Nuclear Material Safety and Safeguards Status - Solicitation being developed 5.
RFP RS-NMS-80-030 Title - Evaluation of Material Accounting Performance at Nuclear Fuel Cycle Facilities Description - Technical support in the collection of specific facility information, support in tha development of input data for material accounting simulation programs, and assessment of the results.
Period of Performance - Three years Sponsor - Office of Nuclear Material Safety and Safeguards Status - Solicitation being developed 6
RFP RS-NRR-80-101 Title - Advanced Reactor Accident Delineation and Assessment Description - This project will provide technical assistance to the NRC in the areas of safety and licensing associated with advanced reacto'r concepts.
Period of Performance - Three years Sponsor - Office of Nuclear Reactor Regulation Status - RFP issue date is August 10, 1979, proposals are due September 14, 1979.
7 RFP RS-NRR-80-102 Title - Energetic Thermal Interactions, Recriticality, and Coolant Flow Phenonena Associated with Advanced Nuclear Reactor Concepts Description - This project will provide to the NRC technical assistance in the areas of energetic thermal interactions and recriticality associated with advanced reactor concepts.
Period of Performance - Three years Sponsor - Office of Nuclear Reactor Regulation Status - RFP issue date is August 2,1979, proposals are due Septenber 5, 1979 ENCLOSURE A L [S8.12 RFP'S ISSUED 1.
Title - Human Factors Evaluation of Control Room Design and Operator Performance at TMI-2 Description - Evaluate control room design, operator training and selection, operator perfornance, and other factors which significantly influenced the sequence of events at TMI.
Period of Performance - Five months Sponsor - TMI Special Inquiry Staff (P,ES Funds)
Status - RFP i ssued July 18, 1979, proposals are due July 25, 1979.
Title - iluclear Reactor Crisis Management-Alternatives for Government Action Description - To provide a listing and an evaluation of alternatives for Government action in nuclear crisis management based on experience in other industry and Government sectors.
Provide comments on draft I;RC-TMI special inquiry evaluation which deal with I:RC's own emergency response.
Period of Performance - Four months Sponsor - TMI Special Inquiry Staff (RES Funds)
Status - RFP issued July 19, 1979, proposals are due July 30, 1979.
3.
RFP RS-0IE-73-257 (Step one of two-step IFB)
Title - Regic, III Mobile Laboratory Description - Special vehicle designed to be used for conducting the confirmatory oeasurements program to evaluate the capability of the licensee to measure radioactivity in effluents.
Period of Performance - liinety days (tentative)
Sponsor - Office of Inspection and Enforcement Status - Request for unpriced technical proposals issued July 20, 1979 Proposals due August 8, 1979.
4 -
RFP RS-ADM-79-651 Title - Production of Source Document-Microfiching and Duplicates Description - Services to produce microfiche including masters with positive-imaged titles and negative-imaged text arc.
and duplicates.
Period of Performance - Twelve months with twelve month option Sponsor - Office of Ariministration Status - IF3 amended July 19, 1979. Bids are due July 31, 1979 5
RFP RS-ADM-79-658 Title - Microfiching Services-Dak Ridge, Tennessee Description - Services to produce microfiche from materials or documents furnished by t;RC but located in Oak Ridge, Tennessee.
Period of Performance - One month from the effective date of contract Sponsor - Office of Administration Status - Solicitation issued July 19, 1979.
Bids are due July 31, 1979.
El CLOSURE A W S013 PROPOSALS U!iDER EVALUATION 1.
RFP RS-f;RR-80-105 Title - Buckling Behavior of Steel Containment Shells Description - The objective of this program is to develop a current staff position on buckling of steel containment shells for fiRC review of applicant designs,
Period of Performance - Two years Sponsor - Office of fluclear Reactor Regulation Status - Proposals sent to Source Evaluation Panel on July 12, 1979 2.
RFP RS-f;RR-79-il8 Title - Engineering Support for Operating Reactor Licensing Actions Description - The f;RC is seeking assistance with its review and evaluation of pending operating reactor licensing actions. Assistance is needed to:
(1) review licensee submittal, (2) perform comparative evaluations relative to established regulatory guides, (3) provide a report documenting conclusions reached and (4) provide a definition of additional information needed to complete the action.
Period of Performance - Three to fivl years Sponsor - Office of fiuclear Reactor Regulation Status - Proposals forwarded to Source Evaluation Panel on July 16, 1979.
3.
RFP RS-ADM-79-390 Title - f;RC Publication Distribution Services Description - Maintaining NRC standard mailing lists and publications inventory.
Fulfillment of I;RC distribution requirements and free requests for copies of f;RC publications and related activities.
Period of Performance - Twenty-four months Sponsor - Office of Administration Status - Proposals received July 10, 1979.
Initial evaluation complete July 20,1979.
4.
RFP RS-ADM-79-399 Title - MPA Management Information Systems Support Services Description - Development, maintenance and/or operation of automated management information systems in support of OMPA objectives.
Period of Performance - One year with two option years Sponsor - Office of Managenent and Program Analysis Status - Proposals received July 20, 1979 and distributed to Source Evaluation Panel for evaluation Ef; CLOSURE A LsSE'yS3 CONTRACT AWARDS 1.
RFP RS-NRR-79-107 Title - Reactor Ccolant Pump / Motor Structural Integrity Following Sudden Seizure Description - The contractor will provide expert technical assistance in evaluating the load carrying capability of the pump-to-motor hold-down bolts to withstand sudden motor seizure of a physical reactor coolant pump.
Period of Performance - Three months Sponsor - Office of Nuclear Reactor Regulation Status - Cost-Plus-Fixed-Fee contract in the amount of $12,709 awarded on July 3,1979 to Shaker Research Corporation of Ballston Lake, New York 2.
RFP RS-ADM-79-386 Title - Development of Automated Personnel System Description - This requirement was set aside for a minority business under Section 8(a) of the Small Business Act. The contractor shall provide anaiysis and design activities required for the development of the NRC Automated Personnel Systom.
Period of Performance - Eighteen weeks Sponsor - Office of Administration Status - A fixed price contract was executed on July 9,1979 with the Small Business Administration and Rehab Group, Inc., an eligible 6(a) minority concern, in the amount of $146,223.72 CANCELLATIONS 1.
RFP RS-NRR-79-110 Title - Decision Analysis Methodology A'plications to the Reactor Licensing p
Process Description - Application of decision analysis methodology within the Office of Nuclear Reactor Regulation in order to develop a nore orderly and more structured process to arrive at regulatory decisions.
Period of Performance - Fourteen months Sponsor - Office of Nuclear Reactor Regulation Status - Cancelled at request of program office ENCLOSURE A L; c hs.,htO 4 c-
UEEi1Y liIGliLIGliTS FOR OPERATIN'3 REACTORS Salen, Unit No.1 At the spent fuel' pool hearing for Salem Unit 1,.ihich resumad on July 10-11, 1979, the ASLB asked the following question u'th regard to the TMI-2 accident:
The Proposed Annex to Appendix D, 10 CFR Part 50, appears to define a Class 9 accident as a sequence of failures which are rare severe than those which the safety features of the plant are designed to prevent. The sequence of failures at Three Mile Island produced a breach of the containment and a release of radiation which could not be prevented by the safety features.
Uas the occurrence at Three Mile Island therefore a Class 'J accident? Uas the risk to health and safety and the environmant " remote in probability," or "extrenely low" at Three Mile Island, as those terms are used in the Annex?
The staff cor.mitted to providing a response to this question by August 3.1979 If.;e do consider the TMI-2 event to have been a " Class 9" accident, the Jaard may decide :o allow testicany from all parties to the Saltm proceeding cn the potential effects of such hypothetical accidents on the Salen expanded SFP.
ichnos Muclear One, Unit flo.1 (ANO-1)
~
A;'0-1 shutdown at 6:52 a.n., July 10, 1979, due to excess vibration in the min turbine.
The plant was at 21" power level at the time with a planned trogram of ascension to narral po ler levals. The turbine previously uperienced vibration in the low prmure area due to turbine blade failure J1ich was repaired in february,1979.
In reviewing the capability of Snubbers at ANO-1, Bechtel Engineering Cor-pration, the A&E for ANO-1, discovered an error was made in the calculations for eight snubbers and two hangers for the main steam line inside the con-tainant.
It was found that the snubbers and hangers were not adequate for
~
arbine trip for repeated cycles.
Bechtel has rcdesigned the snubbers and i 'ngers. Arkansas Pc..er & Light Ce gany (AP&L) have the new components on site.
Installation is expected to be complete by the end of the week.
/.s of July 16, no problem had been found in the turbine.
It is expected that after resetting the balance weights, reascembling the turbine and correcting the snubber and hanger problem, the plant will be ready for s tartup by July 25, 1979.
bM216 ENCLOSURE B Ft. St. Vrain Fort St. Vrain is in the power ascension stage at 10% power.
The moisture in the primary coolant system is thought to be a result of out-gassing from the new fuel blocks which were installed during the first refuel-ing.
The power ascension schedule calls for attaining 28% power by July 20, 19/9 at which point the turbine will be rolled.
It is expected that 40%
power will be reached by July 22nd and 70% power by July 31st.
0'pending on test results, FSV could be permitted to ascend to 100% power oparation in October,1979.
Palo Verde 4&S On July 17, 1979, NRR was notified by Arizona Public Service Company that it had suspended its plans to build Palo Verde Units 4 and 5.
The reasons given were because the participating California utilities found it impossible to continue to participate in view of the questions and objections of the PUC, Energy Ccmnission and Governor Brovin.
Uncertainty of the Federal regulatory process was also cited.
H. B. Robinson Carolina Pcwer & Light Cc:apany has been advised by IE:II not to resume operation of Robinscn until questions concerning t e licensee's response to IE Bulletin 79-02 (Base plate anchor bolt problem) have been acceptably resolved.
At issue here is the bolt failure rate observed from CP&L's testing program req" ired by the Bulletin.
Oconee Nuclear Station Cn July 18,1979 at 7:55 p.m., lightning struck the Greenville, S. C.
substation resulting in isolation of the Greenville to Oconee 230 KV
.ransmission line from the Oconee switchyard.
Prior to isolation there was a voltage swing on the 69 KV bus which feeds the Unit 2 reactor coolant pumps, causing a pump trip on undervoltage.
The Unit 2 generator, turbine and reactor subsequently tripped.
The Unit 2 trip did not result in any upward pressure spikes and posed no challenge to the PORV.
The pressurizer level dropped to 35 inches and returned to normal. The Unit 1 "B" nain feedwater pump suction line simultaneously blew a gasket.
Water from the leak flashed to steam in the turbine building basement.
The steam shorted the control panel for the Unit 1 hot well and booster pumps in the feedwater mystem.
Unit 2 is ceing restored to power operation.
As soon as the Unit 1 blt'in gask;c is replaced that anit will be brought up in power.
The operator sP.sioned in the basement per NRC requirements was uninjured.
This information is preliminary.
u.R;QJ ENCLOSURE B
BI',-lEEKLY STATUS Of.
SHUTDC'.lN PLANTS b(8218 ENCLOSURE B
SEISMIC SHUTD0'.m PLANTS STATUS AS OF 7/18/79 "5 Plant Shutdo.in"
!'AI::E YA*;KEE Restarted 5/24/79 EEA"E?. VALLEY Restart Week of 7/23/79' Seismic reanalysis is complete and modifications are being implemented Problems with feedwater nozzle cracks, and snubber testing FI TZPATP,ICK Restart mid August Licensee submittal for interim operation delayed to 8/3 SURRY l Restart early August Staff review of piping. eanalysis complete.
19 of 63 piping problems require modification to correct overstress.
63 new supports will be installed.
SURRY 2 Restart in November Steam Gen.erator replacement in progress Other Shutdo.in Plants lil7.iOLT 2AY Fault near plant SALEM i Refuelin'g extende~d. Aigebraic Summation problea to be resolved prior to start up.
Baseplate /.kchor Bolt Shutdown Plants
!!ATC:1 1 Restart 8/4 OCO';EE 3 Restart 8/15 CRYSTAL RIVER 3 -
Restart 7/28 FARLEY l Restart 3/8 R03I:;ST; 2 Restart 7/20 Status of P.aview of IE Bulletin 79-07 (Albegraic Summation) eactors utilized Algebraic Summation 29 C
5 plants shutdown by Show Cause Orders 4 plants under construction 20 C;arating Plants status is as follows:
1 Plant refueling outage extended pending reanalysis 3
Plants operating during reanalysis based upon staff evaluation 1
Plant operated 5. leeks to refueling based upon preliminary analysis and meetings with staff 2
Plants reanalysic cor.pl eted by licensee and under staff review 13 Plants resolved and staf f evaluation ccmpleted b i 87,13 ENCLOSURE B
STATUS OF PLANTS SHUTD0'..'N FOR OTHER REASP.d - STATUS AS OF 7)i3/79 J '!,
p Turbin,e Problens Restart 7/25/79
- Arkansas 1 Arkanses 2 Trip
~
Restarted 7/19/79 Big Rock Point 1 Control Rod Crive Leak.
Restart 9/15/79
- Dresden 1 ECCS [bdification Restart 4/80,;/.E GII;M Inspect Feedwater Pipe and Steam Generator l'ozzle Helds Restart 8/6/79 Indian Point 1 ECCS Restart ?
Indian Point 2 Refueling Restart 9/12/79 Kewaunee Refueling Restart 7/25/79 Ocor.ee 1 Grid Trip Restart 7/20/79 Pilgrim Control Rod Drive Line Repair Res tart _7f 2_0/79_._ __]-
-Feed'.:ater Crack Repair Restart 7/21/79 Pt. 52ach 2 Prairie Island 1 Turbine Problems Restart 7/25/79 Three Mile Island 1 Order Restart ?
Three l'ile Island 2 Accident,,
Restart ?.
'O/8220 ENCLOSURE B
(STATUS AS.OF 7/18/79)
FEEDWATER CRACKS PLANTS ILE Sulletin 79-13 dated June 25, 1979 R2quirements: Plant.s with W or CE S/G's complete volumetric exam if FW nozzles uithin 90 days as folloas~:
RT (supplem2nted by UT) of all RI nozzle -to-piping welds &
adjacent pipa & nozzle areas If cracking identified, conduct volumetric exam of all FW line welds up to ist piping support or snubber & snubbers in containment Visual exam of FW system supports & snubbers in contair. ment All PWR facilities perform following inspection at next outage of.
sufficient duration or at next refueling outage after inspection required above.
For S/G's with common nozzle for MFW/AFW conduct volumetric inspection all FW nozzle-to-pipe tield areas & all RI pipe welds inside containment (includes welds connecting AFW to MRI outside containment)
For S/G's uith separate nozzles for MFW/AFW conduct volumetric exam of all welds' inside containment & upstream of external ring header or vessel nozzle of each S/G.
If external ring header used, inspect all welds of one inlet riser on each feedring of each S/G Visual exam of all FW system piping supports & snubbers in containment If indications found in R1 nozzles or piping welds in one unit of a multi-unit facility, otherr: nits cust be shutdu..n and inspected unless justification provided for continued operation.
Report cracking cr discontinuities to I&E region within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Provide schedule for inspections within 20 Jays and adequacy of procedures to respond to a R4 line accident & methods to detect {
Bl leaks in containment.
STATUS:
Plants Inspected:
22 I2 Plants with Cracks:
Plants with Cracks evaluated:
4 restarted:
3 Plants with cracks
! of nozzles with
! of through NRC labs with Plant indications wall Cause Analysis samples Cock l/2 8'of 8 2'
corrosion assisted BNL fatigue 3
Kewaunee 2 of 2 corrosion assisted ENL/L fatigue q;.y Salem 1 4 of 4 Robinson 2 3 of 3 Beaver Valley 1 3 of 3 San Onofre 3 of 3 stress' assisted BSL/L3 corrosion ENCLOSURE B
2_
Pt. Beach 2 2 of 2 stress assisted corrosion Surry 1/2 6 of 6 unkno',in-indications in' feedvlater line
" I slight indication
!! orth Anna 2 1 of 3 may not be a crack Ginna 2 of 2 unkno.in O
9 e
O P-e e
O b
6 6
O l
EfiQLOSURE B
STATUS OF OpERATII;G PLAllT FIRE PROTECTIO!! REVIEl.S The fire protection review of each operating plant results in a license em ndm:nt which places a condition in the license requiring radifications to the plant for the_ addition of fire suppression and detectio.1 systems, installation of fire doors, dampers, and barriers, recabling for separation, for manual fire fighting, and upgrading of adminis-additicnal equipman't trative controls. A safety evaluation report accompanies the amendment and in :ny cases there are a few incomplete items that will require a supple-
- r. ant to the safety evaluation in order to complete their resolution.
The status of the fire protection reviews is as follows:.
Tutal !!u.5er of Plants to be reviewed 53 I:rier of revicws completed 46
!!umbe-of plants remaining 22 i;nSer.of plants to receive amend in July 11 llu:r.ber of plants tc receive amend in Aug.
5 I rber of plants to receive anend in Sept.
6*
Tot [1 !! umber of SER supplements required 49 l rber of SER supplements issued 2
Date by which all SER supplements issued April 1981
':le are attempting to accelerate tites.e reviews into July W
0 d
ENCLOSURE B
OFFICE OF STANDARDS DEVELOPMENT IMPORTANT EVENTS FOR THE WEEK ENDING JULY 20, 1979 1.
Meeting of the Interagency Subcommittee on Radiation Research: A meeting of the Subcommittee on TMI Followup Research, chaired by Dr. A. Upton, NCI, of the Interagency Committee on Federal Research on the Biological Effects of Ionizing Radiation, chaired by Dr. Fredrickson, NIH,was held on July 17, 1979 at NIH in Bethesda.
NRC attendees were J. Foulke, RES, A. Roccklein, SD, R. Goldsmith, SD, and M. Parsont, SD.
Presentations were made by Mr. Todd Frazier, NIOSH, on the NRC/NIOSH cooperative effort to develop a fMI worker registry and dosimetry and health records of TMI workers.
M. Parsont, NRC, presented TMI worker population and individual dose statistics, expanded on Mr. Frazier's presentation and invited member of the Subcommittee to attend the NRC/NIOSH meetirig on July 19, 1979, where these subjects would be more fully presented.
G. Weber, NIMH, discussed the latest--revised protocol for +he mental health survey of people in the vicinity of TMI; and, H. Falk, CDC, discussed the population enumeration study recently completed of the po;ulation within 5 miles of TMI.
The mental health survey protocol has been revised to examine only psychiatric in-and out-patients, young, pregnant women and TMI employees rather than a random sample of persons in the TMI vicinity as previously planned.
There were many questions directed to Dr. Weber to determine why the original protocci was changed and what is the usefulness of the current design. We plan to send a letter to Dr. Upton outlining our concerns with the revised approach as presented by Dr. Weber.
No Subcommi' tee meeting was scheduled for August.
[R. Goldsmith (443-5860)]
2.
NIOSH/NRC Discussion on TMI Worker Registry:
Representatives of N and a
NRC met on July 19, 1979 to discuss Three Mile Island dosimetry programs, and other data necessary for establishing a TMI worker registry. This effort was the first cooperative NIOSH/NRC meeting in response to Secretary Califano's request for such information from Chairman Hendrie.
John Kinneman, Radiation Specialist Region I, presented a comprehensive description of the TMI computer capability in the area of dosimetry records and analyses and information which could be tade available to NIOSH for following health studies.
Also discussed were the EPA /NRC Fear Planning Study and how it will consider TMI as well as privacy resti
.s related to the TMI data.
L iW'0 ENCLOSURE C
_2_
Todd Frazier led the NIOSH team and M. A. Parsont, SD, coordinated the staff participation. Also, in attendance were representatives of NMSS, NRR, ELD, I&E, and the Commission.
John Villforth, Director c f the Bureau of Radiological Health and some of his staff were present.
[M. Parsont (443-5954)]
Publications Issued During the Week of July 16-20, 1979 Draft Regulatory Guide and Value/ Impact Statement: Proposed Revision 1 to Regulatory Guide 1.58, " Qualification of Nuclear Power Plant Inspection, Examination, and Testing Personnel", Task RS 901-5
[ Comments requested by September 28,1979]
Draft Regulatory Guide and Value/ Impact Statement: Qualification Test for Cable Penetration Fire Stops for Use in Nuclear Power Plants, Task
?,S 809-5 [ Comments requested by September 25, 1979]
b '/8225 ENCLOSURE C
OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending July 20, 1979 Shipments of Spent Fuel The first route approved for shipment of spent fuel under the new rule, which became effective July 16, 1970, was for rail shipments between Hartsville, South Carolina and Southport, North Carolina.
The Division of Safeguards is also going to approve on an inteiim basis the continued use of Portsmouth, Virginia, us a port of entry for imports of spent 'uel.
Fortsmouth is a heavily populated area as defined in published staff guidance, and under the rule should be avoided if practicable alternatives are available.
Licensees sa far have been uncole to find ship companies that service ports located in sparsely populated areas.
Clearance Rule In accordance with the Commission's request, a new version of the Clearance Rule has been drafted.
This version excludes nuclear reactors and storage facilities of irradiated reactor fuel from Clearance Rule require -
ments.
The new draft will be forwarded by ELD to the Commission, with ELD's legal opinion on alternative programs under authority other than Sec 161 i.(2) of the Atomic Energy Act of 1954.
Rulemaking Petition Submitted by Edlow International, Inc.
The staff responded to a rulemaking petition submitted by Edlow International, Inc., concerning revisions to 10 CFR Parts 70.20 and 73.37 which would have added carriers as responsible individuals for spent fuel shipments and would have deleted shippers responsible in connection with spent fuel shipments.
The staff determined that the Spent Fuel Rule ;0 CFR 37 would go into effect July 16, 1979, notwithstanding the Edlow petition and that the petition would be considered through the normal rulemaking process.
Safeguards Response to State of Iowa's Rulemaking on Transportation The NRC has been notified by the State of Iowa that it is considering the issuance of regulations for the transportation of shipments of nuclear ma te rial s.
Iowa has invited interested persons, including the NRC, to present written comments and to participate in a hearing which will take place during September 1979.
We are developing alternative safeguards responses for safeguards management to consider in this matter.
Y 8' c~,c,,t.)
fuoI r ENCLOSURE D
Items of Interest 2
NK4SS FY79-80 Program Review Representatives of the Technical Planning and Information Branch participated in a joint 2-day work session at DOE, Gemantown, to review and plan the activity during the balance of FY79 and for FY80 of the Nuclear Materials Management and Safeguards System (NttiSS) contractor.
Personnel from DOE-Germantown, DOE-0ak Ridge Operations, and Union Carbide (the NMMSS contractor) also attended.
Emphasis was placed on the effort needed to meet the nuclear materials reporting requirements under the U.S./IAEA
" Offer" Treaty.
Planning was also initiated for a seminar and workshop to infom and train field and contractor staffs as well as NRC licensees on NMMSS programming and data reporting revisions.
Reoort to Congress on Alternative Fuel Cycles The safeguards chapter of the NRC Report to Congress on the Status of Domestic and International Evaluations of Nuclear Fuel Cycle Systems as mandated by the Authorization Act of 1979 has been prepared and is in the NMSS approval cycle. This chapter presents an overview of 17 candidate fuel cycles being coasidered by DOE, the means applicable to each for safeguarding against proliferation, and the resulting safeguards considerations.
Updating of Radon Value Clarifying information was provided to RES for use by BPNL in completing the interim reports on radon emissions from open pit and underground uranium mines.
Drafts of these reports are expected during the week ending July 20, 1979.
Incident Response Planning The FCMS Incident Response Planning Group has been performing planning and other preparation for the recently announced Environmental Radiation and Emergency Support Section (ERESS) of the Uranium Fuels Licensing Branch and supporting the Emergency Planning Task Force which is re-examining NRC's role in emergency planning.
The Group is currently engaged in both activities in preparing action plans to develop remedies for deficiencies identified in NRC and N!iSS emergency planning by the ad hoc Working Group supporting the Emergency Planning Task Force. The Nf1SS action plans will become part of an overall NRC planning document and the implementation of the remedies identified in the action plan will be among the important activities of the ERESS. A draf t NMSS action plan addressing the nine deficiency items for which NMSS has or shares the lead is due to the Task Force on July 23.
The Task Force has targeted August 3 for delivery of the overall NRC action plan.
! (MC,W ENCLOSURE D
Items of Interest 3
Extension of Comment Period on the Draft GEIS on Uranium Millina The coment period on the Draft GEIS has been extended 60 days from July 26, 1979, to September 24, 1979. This extension has been granted in response to numerous requests.
In addition, regulation changes which incorporate conclusions of the Draft GEIS and implement provisions of the " Uranium fiill Tuilings Radiation Control Act of 1978" are expected to be formally proposed in a couple of weeks.
Since it is essential that the proposed regulation changes and the Draft GEIS be considered together, the comment period has been extended in order to provide adequate time for review.
Trip to DOE Laboratory During the week of July 16-20, Waste Management staff met with DOE labt.ratory personnel at INEL and PNL to discuss work being performed on waste processing and solidification. The meetings are being held to collect test results and expert opinion on the waste form performance of solidification agents for high-level wastes.
Trio to Lawrence Livemore Laboratory (LLL)
During tne week of July 9-13, Waste Managemer.t personnel met with the staff of Lawrence Livermore Laboratory to review work performed to date for NRC on Waste Fom/ Package Perfomance for spent fuel and transuranic wastes.
The review concentrated on focusing the LLL work on developing technical support for regulations and criteria and identifying needed research.
The NRC staff positions regarding: a. the need for multiple barriers in isolation of high-level wastes and b. design criterion for the waste fom/ package was supported by the LLL staff.
The waste / form package is to perform as a principal barrier to the release of radionuclides for the period that the fission products present the principal hazard (mcre than 1,000 years),
u s'S2,'1S ENCLOSURE D
OFFICE OF INSPECTION AND ENFORCEMENT Items of Interest Week Ending July 20, 1979 1.
Preliminary Notifications relating to the following actions were dispatched during the past week:
a.
PN0-79-67AX Three Mile Island Unit 2 - Udated Status Report - This Preliminary Notification was issued so provide updated status information.
b.
PNO-79-241 Washington Public Power Supply Systems Nuclear Projects No. 3 and No. 5 - Allegation of Improper Concrete Placement - A fcrmer employee of a contractor alleged that improper materials had been left in the reinforcing steel during placement of concrete.
IE inspectors will evaluate the adequacy of action taken by the licensee.
(Closed) c.
PNO-79-242 Dresden Statior - Federal Highway Administration Civil Penalty of $10,000 for Shipping Violations - The FHA issued a notice of violation and a proposed civil pencity of $10,000 for violations related to the shipment of radioactive waste.
(Closed) d.
PNO-79-243 Three Mile Island Unit 2 - Two Additional Potential Plant Employee Overexposures Resulting from the Three Mile Island Accident -
During the IE investigation of the March 28, 1979 accident, two additional overexposures to employees were identified.
Both cases involved exposure of individuals' extremities to doses in excess of NRC limits. This matter will be considered further during the IE investigation.
(Closed) e.
PNO-79-244 Calvert Cliffs Unit 1 - Inadvertent Discharge of Acid and Caustic Solutions to the Chesapeake Bay - On July 12, 1979, the licensee inadvertently released about 100 gallons of acid and 160 gallons of caustic solutions to the Chesapeake Bay.
The release occurred as a result of a valve failure in the demineralizer system.
(Closed) f.
PN0-79-245 Rancho Seco - Reactor Trip Resulting From Faultv Pressure Transmitter - The unit tripped from 100% power as a result of a faulty pressure transmitter on a turbine reheater. The transmitter was replaced and the unit was returned to power.
(Closed) g, PN0-75-246 Millstone Unit 1 - Low Sodium Pentaborate for orimary Injection -
Due to an incorrect conversion factor, the procedure for determining the concentration of sodium pentaborate in the Standby Liquid 5torage Tank has yielded a calculated concentration about 15% higher th~n actual concen-tration.
Procedural controls are being modified.
(Closec) h.
PNO-79-247 Pilgrim Station - Undersized Seismic Restraint 3 - The licensee determined that two pipe supports do not meet design specifications. The licensee will modify the supports prior to resuming plant operation.
(Closed)
- i. PNO-79-248 Davis-Besse Unit 1 - Announced Demonstration August 5,1979 Against Davis-Besse - The Toledo Coalition for Safe Energy is organizing an anti-nuclear protest against the Davis-Besse Nuclear Power Station.
The demonstration is planned for August 5, 1979 and is to coincide with the International Nagasaki-Hiroshima Days of Protest.
(Closed) it. SES ENCLOSURE E
- j.
PNO-79-249 Vogtle Unit 1 - Stop Work Order for Reactor Cavity Concrete Placements - Following discovery of inadequate Cadwelds, the licensee issued a stop work order on concrete placement in the Unit I cavity area.
(Closed) k.
PN0-79-250 Westinghouse Electric Corp., Plutonium Fuel Development Laboratory - Electricians Strike Against Westinghouse - The IBEW went on strike at the Cheswick, Pennsylvania site at 12:01 a.m. on July 16, 1979.
On July 17, 1979, the Allegheny County Court issued a restraining order to the IBEW which allowed all personnel not represented by the union to return to work.
(Closed) 1.
PN0-79-251 Palo Verde Unit 1 - Allegations Regarding Use of Improper Weld Material in Reactor Pressure Vessel - Region V (San Francisco) received an anonymous allegation regarding the use of non-ASME approved filler metal in a weld on the reactor pressure vessel. This matter will be investigated at the pressure vessel vendor's facility.
(Closed) m.
PNO-79-252 Arkansas Nuclear One, Unit 1 - Possible Design Deficiency in the Seismic Supports on the Main Steam Lines Within the Reactor Building -
Bechiel infomed the licensee that some snubbers and hangers on the main steam line may have a design deficiency.
The unit is currently in cold shutdown and will remain in this mode pending completion of any required modifications to the seismic supports.
(Closed) n.
PNO-79-253 Arkansas Nuclear One, Unit 2 - Trip of ANO Unit 2 from 50%
Power - During a test of the main steca stop valves, the main feedwater valve failed closed.
Following reduction of generator output, there was a high pressure transient in the secondary steam system that actuated the atmospheric dump valves. The reactor tripped on low steam generator level when a dump valve failed to reseat.
The licensee has repaired the valves.
(Closed) o.
PNO-79-254 H. B. Robinson Unit 2 - Return to Power Operation - Following a refueling outage that began on April 18, 1979, the licensee has returned the unit to operation.
(Closed) p.
PNO-79-255 Waterford Unit 3 - Allegations of Violation of Commission Regulations - A petition was filed in U. S. District Court requesting that the court stop construction of Waterford Unit 3 until the NRC checks out the petitioner's report of " hundreds of violations" of Comission regu-lations.
Region IV (Dallas) will attempt to contact the petitioner and will investigate the allegations for substance, if appropriate.
(Closed) q.
PHO-79-256 Braidwood Units 1 & 2 - Allegation of Improper Concrete Activities at the Braidwood Site - A worker at the site expressed concerns or improper concrete activities.
The worker will attempt to obtain more specific infornation, but can only do so after construction at the site resumes (carpenters are currently on strike).
Region III (Chicago) will followup and attempt to gather specific information as it becomes available.
(Closed)
W S230 ENCLOSURE E
. r.
PNO-79-257 Perry Unit 1 - Small Fire in Containment for Unit 1 - On July 16, 1979, a small fire occurred in the Unit 1 containment building.
Damage was limited to scaffolding and there was no damage to safety related equipment or structures.
(Closed) s.
PNO-79-258 Crystal River Unit 3 - Unqualified Valves Installed Inside the Reactor Building - In accordance with the requirements of IE Bulletin 79-01, the licensee reported discovering four envircnmentally unqualified valves inside the reactor building.
Replacement valves have been ordered.
(Closed) t.
PNO-79-259 Surry Units 1 & 2 - Rejectable Welds in Feedwater System -
During radiography of feedwater piping welds of Unit 1 as required by IE Bulletin 79-13, seven welds have been found to have rejectable indi-cations.
The licensee plans to repair the welds prior to startup.
(Closed) u.
PNO-79-260 Browns Ferry Unit 3 - Hydrogen Detonation in Off-Gas System -
Following a reactor scram on July 17, 1979, unstable recombiner operation resulted in increased hydrogen concentration and a subsequent detonation in the off-gas system.
No personnel injuries or contamination a rred.
(Closed) v.
PiiO-79-261 Indian Point Unit 2 - Allegation of Unsafe Work Practices at Plant - An allegation was received by Region I (Philadelphia) of unsafe physical and radiological work practices at the plant.
This matter will be reviewed by the Resident Inspector.
(Closed) w.
PNO-79-262 United Nuclear Corporation, Wood River Junction, RI - Tri-State Trailer Carrying LSA in Connecticut - Connecticut officials temporarily impounded a Tri-State trailer carrying radioactive materials from the United Nuclear Corporation.
This action was taken because the tractor did not have license plates and the temporary Illinois registration of the tractor had expired.
The unit was subsequently released.
(Closed) x.
PNO-79-263 Duane Arnold - Reactor Scram on Turbine Trip - Reactor Shutdown for Greater than 48 Hours - On July 18, 1979, the reactor scramed from 100% power due to a turbine trip which was caused by an exhaust hood high tempera ture.
(Closed) y.
PNO-79-264 Hatch Units 1 & 2 - Interest in Environmental Report - A member of the Georgia Public Service Commission discussed the Georgia Power Co.
Annual 1978 Environmental Surveillance Report with reporters on July 17, 1979.
The principal issue was elevated tritium levels in environmental sample wells onsite and measured tritium levels in two outfalls outside the restricted area but within the Georgia Power Co. property.
(Closed) z.
PNO-79-265 Oconee Units 1 & 2 - Reactor Trip Due to Grid Fault - On July 18,1979, Unit 2 tripped due to a turbine trip caused by a grid fault.
The grid fault resulted from a lightning strike on a switchyard.
During the transient, a gasket on one main feed water pump failed causing a steam leak into the turbine building basement. As a result, a Unit 1 electrical panel was lost causing a temproary loss of Unit I hot well pumps and conden-sate booster pumps.
(Closed) bdQ ENCLOSURE E aa.
PNO-79-266 Brunswick Unit 1 - Reactor Trip - The reactor tripped from 60% power while attempting to place recirculation pump 1B in service.
The pump had been stopped at 11:30 p.m. on July 18 due to a failure of the motor generator set lubricating oil system.
Following resolution of the oil system problem, the pump was restarted. While opening the pump discharge valve, the average power range monitor spiked and a reactor trip occurred. An investigation by the licensee and the Resident Inspector is being conducted.
(Closed) bb. PN0-79-267 Arkansas Nuclear One, Unit 2 - Trip of ANO Unit 2 from 50%
Power - On July 19,1979, Unit 2 tripped from 50% power on low steam generator level. The licensee concluded that the low steam generator level resulted when an operator leaned against the control panel and caused the main feedwater pump turbine to runback to the low speed stop.
(Closed) cc.
PNO-79-268 Brunswick Unit 2 - Planned Shutdown - The licensee removed the unit from service to replace a Target Rock relief valve that opened without cause twice within two days.
(Closed) dd.
PNO-79-269 McGuire Units 1 & 2, Catawba Units 1 & 2 - Duke Power Company announce a delay in completion of four reactor at two sites. The delays range from six months to two years.
(Closed) ee.
PNS-79-75A & -75B Nuclear Fuel Services, Erwin, TN - Arrest of Union Members During Operators Strike - Union members expressed intent to travel to Washington, D. C. to picket NRC and DOE offices.
(Closed) ff.
PNS-79-76 Wolf Creek Urit 1 - Bor.b Threat - A search of the plant site was conducted with negative results.
(Closed)
- 2. The following IE Circualrs were issued:
a.
IE Circular 79-13, "Replacemut of Diesel Fire Pump Starting Contactors,"
was issued on July 13, 1979 to all power reactor facilities with an operating license or construction pemit.
b.
IE Circular 79-14, " Unauthorized Precurement and Distribution of Xe-133,"
was issued on July 13, 1979 to all medical licensees except teletherapy medical licensees and to all radiopharmaceutical suppliers.
- 3. The following IE Information Notices were issued:
a.
IE Information Notice 79-18, " Skylab Reentry," was issued on July 6,1979 to all holders of reactor operating licenses.
b.
IE Information Notice 79-19, " Pipe Cracks in Stagnant Borated Water Systems at PNR Plants," was issued on July 17, 1979 to all power reactors with an operating license or construction permit.
U [S2.32 ENCLOSURE E
5 0FFICE OF THE EXECUTIVE LEGAL DIRECTOR ITEMS OF INTEREST FOR THE WEEK ENDING JULY 20, 1979 Kewaunee Nuclear Power Plant On July 17, the Administrative Law Judge approved the settlement reached by the Staff and the Licensee and thereby terminated the civil penalty proceeding.
Under the terms of the settlement, the Licensee makes certain admissions regarding the Staff's allegations, agrees to pay the penalty of $7,000 and to withdraw its request for a hearing.
In turn, the Staff agrees that the incident resulting in items of noncompliance was an isolated act and not a general reflection on the Licensee's management or personnel.
ENCLCSURE G G78233
ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING JULY 20, 1979 INTERNATIONAL COOPERATION Meeting Announcement On Tuesday, July 24, IP is scheduling a 9:00 to 10:00 a.m. appointment for Mr. Bruce P. H. Chu, Vice President of Taiwpower, and three members of his staff to discuss NRC export licensing policy in the long term as it relates to phase-two of Taiwan's nuclear program.
The session will take place in H-ll67.
On Tuesday and Wednesday an eight-member delegation of the French Nuclear Safety Protection Institute (SCSIN), headed by Mr. Tanguy the Director, met with staff members of NRR, RES, SD, and IP to discuss the incident at TMI-2, including its relationship to the French nuclear program.
On Thursday Dr. A. B. Lidiard of the U.K. Atomic Energy Research Establishment at Harwell met with Dr. C. Z. Serpan of RES to discuss (1) research programs relating to the integrity of reactor pressure vessels, (2) material cccurrences of cracks in weldings, (3) the efficiency af inspection procedures, and (4) the study of PWR vessel integrity in general.
EXPORT / IMPORT AND INTERNATIONAL SAFEGUARDS Udall Hearings IP is preparing testimony for Chairman Hendrie to be presented before the Udall Committee on July 26.
The hearings will deal with Nuclear Proliferation and NRC's role in implementing the US policy.
k.3234 ENCLOSURE H
0FFICE OF STATE PROGRAMS ITEMS OF INTEREST _
WEEK ENDING JULY 20, 1979 State Agreements The Kansas radiation control program will be reviewed during the week of August 30, 1979.
Program Development Letters of invitation to Governors, State legislative leadership and State public utility chairmen were mailed for the Workshops on State Review of NRC Decommissioning Policy. These will be held in Columbia, South Carolina September 12-14 and Seattle, Washington September 25-27.
On July 13, 1979, Tom Elasser met with Commissioner Kenn'.dy to discuss the issues raised at the National Governor's Conference hr' 2 on July 9,1979.
Emergency Preparedness Final arrangements were made by R. DeFayette to visit Vermont, New Hampshire, Massachusetts and Maine in early August to discuss development of emergency plans in each State.
Arrangements are also being made to present the Radiological Emergency Re-sponse Plenning course to Illinois personnel in Springfielc during the week of September 10, 1979.
Robert DeFayette represented NRC on a panel discussion on aspects of nuclear energy at the annual meeting of the National Association of Counties in Kansas City, Missouri.
A report to the Commission was prepared on the efforts to accelerate the development of State and local government radiological emergency response pl a ns. The report will be updated and submitted monthly to the EDO.
The Emergency Preparedness staff is working with the State of Maryland Division of Radiation Control and Office of Civil Defense to identify the categories of nuclear facilities that should be covered in the States' Radiological Emergency Response Plan.
Current thinking is that although there are four licensed research reactor facilities within the State, the primary effort will be to develop a coordinated plan with Calvert County and the nuclear power reactor at Calvert Cliffs.
Messers Bajwa and Dukes met with Nebraska Civil Defense officials in Lincoln on July 11 and 12 to discuss implementation of the Peacetime Radiological Emergency Response Analysis Device on the Nebraska plan.
Most of the time was spent deciding the correct sequence and timing of the emergency response by the various Nebraska organizations.
Organizational L lE5'U.3 ENCLOSURE I
. responsibilities were well defined in the plan. The plan had been revised and reprinted, and in the process of collation at the time of the visit.
Mailing to NRC is expected soon. An Exercise is scheduled for July 31 this year.
Hal Gaut, SP, Mal Ernst, and Jim Herr of the NRC/Tf1I Investigation Group and Tom Elsasser, SP (Region I-SLO) met with State and local officials of Pennsylvania to review State and local activities in the TMI emergency re-sponse operations.
Bill Axelson, NRC Region I, headed a Federal Interagency Regional Advisory Committee assistance visit to Wisconsin to review the State plan.
On July 17, 1979, Tom Elsasser met with Maryland State Officials in Baltimore and Pikesville, Maryland to discuss emergency response planning and other areas of mutual interest to Maryland ard the NRC.
On July 18, ? 979, Tom Elsasser met with Maryland State Officials in Annapolis ta discuss e ergency response planning and other areas of mutual interest to Maryland and the NRC.
L ;Nr?']th ENCLOSURE I
OFFICE OF MANAGEMENT AND PROGEM ANALYSIS Items of Interest Week Ending - July 20, 1979 Information_ S1orage and Retrieval for Incident Response MPA has been exploring informally certain Defense Department (ARPA) advanced image storage and retrieval techniques for possible application to NRC incident response.
The advanced techniques are embodied in videodisc, a system that can store up to 54,000 picture frames per disc for instantaneous recall, e.g. internal or external parts of a reactor or schematics.
A meeting was held during the week with ISE staff to review the Incident Response Center and discuss techniques of data collection and retrieval, including video-disc. A task force has been formed to evaluate possibilities of using the video-disc in conjunction with other capabilities at the Incident Response Center.
The task force will consist of members from RES, NRR, f4 MSS, I&E, and MPA. The task force will meet to review the capabilities of the videodisc system next week.
After reviewing this system and the feasibility of using it for incident response purposes, presentations to the EMT will be scheduled.
Provisions of NRC Authorization Bills At request of OCA, transmitted an abbreviated outline of the major provisions of fiRC's authorization bills, H.R. 2608 and S. 562.
Nuclear Plant Reliability Data System MPA staff attended July 17-18 meeting of the ad hoc subcommittee of the ANSI N18.20 Subcommittee to review the analytical techniques for the 1979 NPRDS annual report.
The important changes which we sought were adopted by the ad hoc sub-committee; in particular, to include the "no failures" in failure rate calcula-tions, to summarize variability of failure rates over plants, and to use unbiased estimates of failure rates.
D3cuments for President's Commission on TMI The final shipment of documents requested by the President's Commission in its letters of June 28 and July 2 was made on July 19.
L,.M37 ENCLOSURE J
4 Office of the Controller Items of Interest Week Ending July 20, 1979 Budget Formulation The EDO completed his mark on the FY 1980 budget supplemental and the FY 1981-1983 budget.
The EDO recommended budget will be submitted to the Commission on July 23.
FY 1980 Budget The Senate passed NRC's FY 1980 Appropriation bill for a total of
$363,340,000, which is $5,000,000 more than the House Appropriation bill.
The House and Senate plan to go to conference on July 24.
FY 1979 Reprogramming The staff of the House Subcommittee on Energy and the Environment was briefed on reprogramming paper #3.
To date, the staffs of three Subcommittees have been briefed.
Enclosure K kliF2'if3
CALEt4DAR OF SIGNIFICANT EVEflTS July 23,1979 Skagit 1 & 2 - The safety hearings will begin July 27,1979 Salem 2 - ACRS Subcenr.ii. tee meeting to discuss impact of the TMI-2 accident on the Salem Nuclear Power Station, Unit 2 Three Mile Island - Meeting of ACRS Ad Hoc Subcommittee b/f52i}9 ENCLOSURE L
CALENDAR OF SPEAKING ENGAGEMENTS AUGUST Augas t o-10 Lecture the IE Inspectors on Concrete and Other Structural Defects Experienced in Nuclear Power Plant Construction -
L. L. Beratan SEPTEMBER September Nuclear Records Management Association Symposium, San 12-13 Francisco, CA - Two RV Staff Personnel to Participate on a NRC Panel for two Question / Answer Sessions September 16 ANS Topical Conference on Decontamination and Decommissioning of Nuclear Facilities, Sun Valley, ID - Residual Activity Limits for Unrestricted Release from Decommissioning - E. Conti em240 ENCLOSURE N