ML20009F246
| ML20009F246 | |
| Person / Time | |
|---|---|
| Issue date: | 07/28/1981 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-810724, NUDOCS 8107300199 | |
| Download: ML20009F246 (30) | |
Text
.-
^J A C FDA 1
' July 28,,1981
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3For:
The Comissioners From:
T. A. Rehm : Assistant ~for Operations, Office of_-the ED0
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING JULY 24, 1981 A-sumary of key events-is included as 'a ~ convenience.to those Comissioners who may prefer a condensed version of_this report.
Contents
- Enclosure Administration A
Nuclear Reactor Regulation B
jT((f-0[l.Ju. '
Kg\\ 3 Nuclear Material Safety and Safeguards C
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'I Inspection and Enforcement D-
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.9-,
JUL 2 91981 * $
Nuclear Regulatory Research E
3 v.s.eagg52 6 Executive Legal Director F*
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International Programs G
State Programs H
Management and Program Analysis I
Controller J*
Analysis and Evaluation of Operational Data K
c Small & Disadvantaged Business Utilization L*
Items Approved by the Comission M
T. A. Renm, Ass r Operations-Office of the Executive Director for Operations
- No input this week.
Contact:
l T. A. Rehm, EDO 49-27781
+
8107300199 810728 PDR.COMMS NRCC WEEKLYINFDREPT PDR b
Sunmary of Weekly Information Report Week Ending July 24, 1981 Sequoyah 2.
TVA estimates that Sequoyah 2 will go critical' on August 23, 1981, and begin power escalation tests on September 3, 1981.
R.E. Ginna A 55-gallon low-level waste drum, recently_ shipped from Ginna to the Beatty, Nevada burial site,~ was found to have a small puncture'near the rim where the lid is attached. The cause of the puncture is believed to be a defective part on the loading rig at the Ginna site. Although no contamination was found, the State of Nevada fined the licensee $1500.00 and suspended its permit for three months.
Maine Yankee Maine Yankee commenced its 6th cycle of power operations on July'25',1981, af ter
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a 63-day refueling outage.
Various plant modifications were also made.
United Nuclear Corporation (UNC) - Wood P.tver Junction, Rhode Island On July 16, 1981, NRC staff met with Congresswoman Claudine Schneider of Rhode Island to discuss the decommissioning of the UNC facility. Mrs. Schneider's main concerns were (1) the groundwater contamination caused by a leak in the UNC_ lagoon liners and (2) the disposal of the solid waste and rubble accumulated during the decontamination process.
Mispissippi Power and Light Company (licensee for Grand Gulf plant)
NRC !ssued a license to the Grand Gulf licensee for the receipt, possession, inspection and storage of uranium enriched in the U-235 isotope contained in fuel assemblies and in fission chambers.
Proposed Rule - 10 CFR Pai. 61 Proposed Rule - 10 CFR Part 61, " Licensing Requirements for the Land Disposal of Radioactive Waste," will be published in the Federal Register on Friday, July 24,1981.
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OFFICE OF ADMINISTRATION Week Ending July 24, 1981
_ ADMINISTRATION OF THE. FREEDOM 0F INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Received 328 11 Granted 234 E
Denied 42 7
Pending 52 2
ACTIONS THIS WEEK Received K. E. Fischer, Requests three categories of information related to University of nuclear waste management on Palmyrc, Atoll, Midway, California Wake or any other Pacific Island.
1 (81-271)
(NRC employee)
Requests the names of individuals and their Candidate (81-272)
Evaluation Certification and Selection Records for Vacancy Announcement 81-2112.
Terry Horne, Requests all dacuments pertaining to the establishment Birmingham Post-Herald or future development of a nuclear waste storage (81-273) or disposal facility in the State of Alabama and the namen of all such facilities in the US now under development or consideration as well as the names and cddresses of companies involved.
(NRCemployee)
Requests information on him from Personnel, Office of (81-274)
Inspector and Auditor tid any charges made against him.
Steve C. Briggs, Requests a copy of NUREG-0706, Volume III.
Hutchinson, Black, Hill, Buchanan & Cook (81-275)
Philip C. Henry, Requests information on Thorotrast.
Phillips, Hart & Mozley (81-276)
CONTACT:
J. M. Felton 492-7211 ENCLOSURE A
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' Received,-Cont'd R. B. Borsumi Requests a copy of SECY-81-25, " Consideration'of
' Babcock & Wilcox.
Probabilistic ~ Risk Assessment ~ (PRA) for SONGS 2 and 3."~
(81-277)
- Mae Lynda Billingslea,-
Requests the number of employees in the:NRC; the
~ National All;ance of name of the organization having;exclusiv_e recognition Post and Federal Employees and.the date the contract expires; a copy of the NRC's (81-278)
Affirmative Action Program and the name of.inoividual(s)-
for future contracts,-including address and telephone number.
Steven J. London, Requests, on behalf of his client, four categories Lester Schwab Katz.
of information regarding reports of exposure to
& Dwyer radiation for the quartec ending 9/30/76 at the-(81-279)
Indian Point II Station.
K. E. Fischer,
' Requests four categories of documents relating to University of
" Working Group 6 of the International Fuel Cycle California Evaluation" that deals with the general problem of (81-280) spent fuel.-
fJames S.' Oppenheim, Requests a list of the names of individuals.
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Business Publishers, Inc.
corporations and state agencies involved with nuclear ~
(81-281) waste processing and fusion power research and i
demonstration.
'(An individual requesting Requests information on his Reactor Operator License.-
information about himself) written and oral examinations.
(81-282)
Jo Ann Shotwell, Requests eight categories of documents regarding
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The' Commonwealth of emergency planning for Pilgrim I and II.
Massachusetts (81-283)
Joanne Dann, requests a copy of SECY-81-312, SECY-81-231, McGraw-Hill Publications correspondence relating to these SECY papers and Company, Inside NRC a list of investigations conducted by the Office of:
(81-284)
Inspector and Auditor since January, 1981.
.Marsha Walls, Requests a mailing or distribution list pertaining Technical Insights, Inc.
to recombinant DNA research maintained by or for the (81-285)
NRC.
'(An individual requesting Requests information on his Reactor Operator License information about himself) written and oral examinations.
(81-286)
O ENCLOSURE A
3 Gra r'ed
- - (NRC employee)" ---
In response to a request' for a ' copy of a named (81-242) individual's letter of resignation, made available a copy of this document.
Patricia Hinsberg, In response to a request for a copy of SECY-81-253, McGraw-Hill Publications
" Financial Protection for TMI Units 1 and 2,".made Company available a copy of this document and a memo regarding (81-251) this SECY paper.
Van M. Lowry, In response to a request for copies of records The Dow Chemical pertaining to NRC policy and procedures for handling Company and safeguarding confidential business information, (81-253) made available pertinent information.
Raymond W. Schowers, In response to a request for all reports from Stan A.
Sutin, Thayer and Huber Consultants, Inc. to Nuclear Pharmacy from Browne February 14, 1978 through Februar,, ~29,1980, made i
(81 258) available 19 documents.
(An individual requesting In response to a request fcr specific infonnation information) pertaining to candidates selected for Vacancy (81-259)
Announcement R81-3119, made available the requested information.
Brian C. James, In response to a request for documents regarding The Bendix Corporation existing and pending applications of a gas and (81-260) aerosol detection device containing Americium-241 having a source strength equal to or greater than f>:,3 microcuricc, made available nine documents.
Robert Alexander, In response to a request for 11 listed documents, Mockingbird Alliance made available a copy of these documents.
(81-262)
(An individual requesting In response to a request for information on herself information about herself) in the NRC, informed the requester the NRC has no (81-266) records pertaining to her.
Steve C. Briggs, Made available a copy of NbREG-0706, Volume III.
Hutchinsen, Black, Hill, Buchanan & Cook (81-275)
ENCLOSURE A
., Denied Ellyn R. Weiss, -
In response to a request for all docum'ents' relating Union of Concerned to Southern Boiler and Tank Works, Inc.,~ made Scientists available 11 documents.
Informed the requester five (81-245) additional documents subject to this request are already available at the PDR.
Denied portions of one document containing confidential business (proprietary) information. Denied portions of another document containing advice, opinions and recommendations of the staff.
Denied four documents in their entirety containing advice, opinions and recommendations of the staff.
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-i ENCLOSURE A
A DIVISION OF CONTRACTS ~
Week Ending July 25. 1981
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CONTRACTS CLOSED OUT (All administrative action completed and final payment made)
Contract No.
-Contractor Close-out Date NRC-03-76-309 Nunn. Snyder & Assoc.
7/21/81
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7/20/81 NRC-05-77-146 Portinnd Cement Assoc.
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NRC-19-81-491 Teknekron Research 7/20/81 NRC-10-78-583 Montgomery County Public 7/21/81 Schools NRC-10-81-360 Mr. D. Matthews 7/21/81 NRC-03-80-137 Human Design Group 7/23/81 i
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ENCLOSURE-A
DIVISION OF RULES AND RECORDS OFFICE OF ADMINISTRATION The Executive Director for Operations has issued a minor amendment to withdraw an Advance Notice of Proposed Rulemaking (ANPRM) published in the Federal Regis~ter on April 17,1979 (44 FR 22746) as an experimental
" plain English" revision of the Freedom of Information Act regulations in 1C CFR Part 9.
This action was-taken in light of staff initiation of.a periodic and systematic review of all NRC regulations as required by the Commission as part of the TMI Action Plan.
Comments received on the ANPRM are being considered in formulation of proposed revised F0IA regulations during the review of all of Part 9.
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l ENCLOSURE A
F DIVISION OF. SECURITY.
Week Ending July 24, 1980'
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Personnel Security Program Review
- The-Division of Security.has initiated a comprehensive r,' view of the NRC Per-sonnel Security Program with the objective of designing a nore efficient and--
cost-effective program..This review.is-to be completed by January 1,11982.
Security Support for ASLBP The Division of Security provided security support in connection with the
- Susquehanna Prehearing held in Wilkes-Barre, PA. This support involved arranging for Federal Protective Officer coverage of the hearing.
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l ENCLOSURE A L:- -
OFFICE OF NUCLEAR REACTOR REGULATION
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... EEK ENDING JULY. 25, 1981 W
SEQUOYAHJ TVA now estimates criticality on August 73, 1981 and all Physics tests completed by September 2,1981.
Power escalation tests (above 5% Power level) could'begin on September 3,1981.
The revised schedule was provided by TVA on July 17, 1981.
The schedule is based on resolving all deficiencies on our IE list and the removal of the jammed RV stud.
One of the 54 threaded studs (6 3/4" diameter) jammed approximately 5" into the RV flange.
Attempts to remove the stud have failed; therefore, an outside contractor will work on the removal and possible repair of the threaded hole in the flange.
R. E. Ginnt.
Rochester G:s and Electric. Corporation (RG&E) recently shipped 43.55-gallon orums of low specific activity waste from Ginna to.the Beatty, Nevada burial site.
During off-loading and receipt inspection one drum was found.
to have a small puncture near the rim where.he lid is attached.
Offloading was halted, RGLE was called, and RGLE dispatched a ~ health physicist to Nevada.
His exarninatio'. showed no contamiriation either inside or outside the drum, which contained materiaT solicifico oy a mixture of concrete and vermiculite.
No other problems were noted during the officad.
In spite of this, the State of Nevada has fined RGLE $1500.00 ano has' suspended their permit for 3 months.
RGLE has determined that the cause of the puncture was a defective part on the' loading rig at the Ginna site.
It will be replaced.
MAINE YANKEE ATOMIC POWER STATION Maine Yankee commenced its 6th cycle of power operations on July-20,1981 after a 63 day refueling outage.
Actions included during the cycle 6 refueling outage wer.e; 1) Fuel loading for a 13 month power cycle, 2) replacement of one low pressure (LP) turbine rotor.
Blades were removed fram a second LP turbine disk and replaced by a shroud to maintain correct pres:ure drop, 3) addition of a steam driven main feedwater pump and 4) revision of reactor vessel fluence figures in the technical specifications.
Other plant modifications based on NRC requirements were the addition of a' check valve in each safety injection line and Technical Specifications for surveillance of the check valves.
The modifications are in compliance with NRC Confirmatory Order dated April. 20, 1981.
ENCLOSURE B
i NRR WEEKLY HIGHLIGHT -
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MEETI G NOTIFICATION There will be an NRR meet.1g with the Babcock & Wilcor, Combustion Engineer, and Westinghouse NSSS Owners Groups to discuss the Thermal Shock to Reactor Pressure Vessels.
Scheduies are as follows:
Time d Dath:
B&W Group Westinchouse Group CE' Group July 28, 1981 July 29, 1981 July 30, 1981 1:00-4:15 r.m.
1:00-4:15 p.m.
1:00-4:15 p.m.
Location:
P-422 P-110 P-ll8 Phillips Building Phillips Building Phillips. Building _
Bethesda, MD Bethesda, MD Bethesda, MD TMI PROGRAM OFFICE
' Met-Ed has announced that the current Director - TMI-2,' Gale Hovey has announced his intent to resign.
A replacement is being sought, and Met-Ed expects that Hovey will remain until his replacement is available and an orderly transition is accomplished.
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ENCLOSURE B
-NRC TMI PROGRAM OFFICE WEEKLY STATUS REPORT W;sk of July 19 - 25, 1981
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Plant Status Core Cooling Mode: Heat transfer frem the reactor coolant ::ystem (RCS) loops to Reactor Building ambient.
Availabic Core Cooling Modes:
Decay heat removal systems.
Iong term cooling "B" (once through steam generator-B)
~RCS Pressure Control Mode:
Standby Pressure Control (SPC) System.
Backup Pressure Control Modes:
Mini Decay Heat Removal (MDHR) System.
Decay Heat Remaval (DHR) System.
Major Parameters (as of 0500, July 23,1981) (approximate values)
Average Incore Thermocouples: 120*F r
luximum Incore Thermocouple:
143*F RCS Loop Temperatures:
A B
Hot leg 120*F 122*F
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Cold Leg (1) 73*F 75"F (2) 74*F 75'F RCS Pressure:
92 psig Reactor Building:
Temperature: 76*F
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Water level:
Elevation 290.9 ft. (8.4 ft. from ficor) via penetration 401 manometer j
Pressure:
-0.15 psig Concentration:
4.6 x 10-6 (LLD) uCi/ml Kr-85 (Sample taken 7/23/81)
Effluent an_d Environmental (Radiological) Information 1
Liquid ef fluents 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.
l During the period Jcly 17, 1981, through July 23, 1981, the effluents contained no detectanle radioactivity at the discharge point although individual effluent sources which originated within Unit 2 contained minute amounts of radioactivity.
Calculations indicate that less
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than 1 millionth (0.000001) of a curie of Cs-137 was discharged.
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This represents less than 0.00001% of the permissable total liquid activity as specified in Technical Specifications for operational commercial reactors.
Calculations also indicate that less than 1 tenth (0.1) of a ci of Tritium (H-3) was discharged.
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2.
Environmental _ Pro 2ection Agency (EPA) Environ.nental Data.
Resul ts.
from E. A monithring of the environment around the TMI site were as follows:
H 3
The' EPA' measured Kr-85 concentrations (pci/m ) at several environmental monitoring stations and reported the following results :
Location June 26 - July 3,1981 3
(pCf/m )
. Goldsboro 26 Observation Center 27 Hiddletown 28 Yorkhaven 28 All of the above levels of Kr-85 are considered to be back-ground levels.
No radiation above normally occurring background levels was 1
detected in any of the samples collected from the EPA's' air 2
and gamma rate networks during the period from July 16.-1981,
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thrnugh July 23, 1981.
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NRC Envi r_o_nmental Da ta_.
Results from NRC monitoring of the environ-ment 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 (uti/cc)
(uC1/cc)
HP-277 July 15,1981 - July 22,1981
<8.6 E-14 <8,5 E-14 4.
Licensee Radioactive Material and Radwaste Shipments.
On Honday, July 20,1981, a 40 ml Unit 2 reactor coolant sample was sent to Babcock and Wilcox (S&W), Lynchburg, Virginia.
On Friday, July 24, 1 981, two Hittman steel liners containing Unit I solidified evaporator bottoms were shipped to U.S. Ecology, Richland Washington.
Major Activities
.N 1.
Submerged Demineralizer System _ (SDS).
Processing of the first batch (approximately 50,000 gallons) of intermediate radioactivity level water from the Auxiliary' Building Reactor Coolant Bleed Tank (RCBT) was completed on July 19, 1981.
Preliminary results indicate that the first batch resulted in a loading of approximately 320 curies of Cs-137 and 160 curies of Sr-90 on the first ion exchange vessel.
ENCLOSURE B
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'b This represents greater than 99% removal of these radioactive
,j materials from the process stream.
Frocessing of the second batch a
(approximately 50,000 gallons) of RCBT water commenced on July 23, 1981.
After the RCBT water is processed, the SDS will be used to process.
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I f gh level Reactor Building sump water.
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2 Reactor Buidling Entry.
Four teams, a total of nine pecple, entered
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the Unit 2 Reactor Building during entry number fourteen (designation J
change) on July 23, 1981.
Team four included the first woman into the Reactor Building since beginning the Reactor Building entries last year.
The following tasks were successfully completed.
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Maintenance of the closed circuit TV system 7
.y Removal of the Core Flood Tank "B" Transducers Photographs of air cooler e uipment and components of the reactor fluid make-up system Radiation survey of the shallow end of the refueling poob Miscellaneous sample wilection Installation of two radiation area monitors 3.
EPICOR-II_ Second and Third Stage Mners.
On June 30,1931, the
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last two (of twenty-two) second and third stage EPICOR-II liners I
reached the burial site in Hanford, Washington, as reported in the Weekly Status Report for the week of June 28 through July 5,1981.
These liners were generated during the processing of contaminated water through the EPICOR-II system.
The EPICOR-II system was used to process Auxiliary Building water (approximately 500,000 gallons) from the N rch 28, 1979 accident.
Regional inspectors from the U.S. Nuclear Regulatory Commission's
-l' Region V office in' Walnut Creek, California, have visited the Hanford burial site for inspection purposes.
The inspectors have concluded, based on physical verification of the burial of the 22 liners, and proper documentation, that all applicable -tuviel Mts criteria were satisfied for the THI wastes.
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. OFFICE OF li' CLEAR MATERIAL SAFETY AND SAFEGUARDS Items-of Interest Week Ending July 24, 1981 United Nuclear Corporation (UNC) - Wood River Junction, Rhode Island On July 16, 1981, E. Fay, CA and W. T. Crow, NMSS met with Congresswoman Claudine Schnieder of Rhode Island to discuss the decormiissioning of the United Nuclear Corporation (UNC) facility at Wood River Junction, Rhode Island.
Mrs. Schnieder's main concerns were (1) the grcund water contamination caused by a leak in the UNC lagoon liners, (2) the disposal of the solid waste and rubble accumulated during the decontamination prccess.
Regarding the ground water con-tamination, Mrs. Schnieder was told that the NRC is evaluating the aquifer contamina-tion to see if we can predict how long it will take for it to purge, itself naturally to background concentrations and secondly, what, if anything, can be done to enhance the purging of the aquifer. This study should be complete by the end'of the year.
With regard to the solid wastes stored on site, Mrs. Schnieder was inforrhed that UNC had _ petitioned DOE to assume responsibility for disposal under P.L.96-573 and UNC was postponing shipping to a licensed burial ground until they heard from 00E.
Kerr-McGee West Chicago Site A meeting was held with representatives of Kerr-McGee to discuss whether.an EIA or EIS should be used to support licensing action on Kerr-McGee's proposed stabilization plan for their West Chicago site.
It was concluded that an EIS would be issued. A preliminary draft EIS has been prepared by Argonne National Laboratory and internal comments on the draft are being prepared by NMSS.
Mississippi Power and Light Company Materials License No. SNM-1882 for the Mississippi Power & Light Company was issued on July 15, 1981.
ThelicenseauthorgUisotopecontainedinfuelassem-s the receipt, possession, irspec-tion arid storage of uranium enriched in the blies and in fission chambers.
It also authorizes the receipt, possession and use of Sb-Be neutron sources.
The license is for Unit 1 of the Grand Gulf Nuclear Station located in Claiborne County, Mississippi.
License Renewal Applications The Material Licensing Branch has conceived and developed an idea to prepare license renewal applications for certain medical licensees much the same way that IRS prepares tax returns for certain classes of wage earners.
Preprinted forms and sample procedures from the medical licensing guide are used, thus conserving NRC resources.
ENCLOSURE C
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License Renewal Applications (cont'd)
Licensees benefit by'saving staff time or fees to consultants for prepar.ing appli-cations. NRC benef1ts by eliminating the tedious review of page after page of printed matter that most licensees submit. All present assurances of health and safety are retained while 'providing regulatory relief and reducing NRC review time.
If successful, this method may be expanded to include certain calsses of industrial
-licensees, and the preprinted applications may eventually.be prepared by a computer.
As part of the initial trial program, the first batch of preprinted applications-was mailed u,a July 15.
Recipients were informed that participation is voluntary.
Progress wil'. be reported periodically.
INMM.14 Subconnittee on International Standards On-July 12, Safeguards representatives a+'.e.ided the INMM.14 Subcommittee meeting.
Participants from IAEA, GE, AGNS, PNL, Bht, and ISP0 reviewed the international standard being prepared on Physical Inventory Taking and Verification, which was prepared by the subcommittee's three working groups. This initial draft will be
- revised for review and integration at the next meeting, tentatively scheduled for November 1981 at the NRC.
't Proposed Rule - 10 CFR Part 61 Proposed Rule - 10 CFR Part 61 " Licensing Requirements for the Land Disposal of Radioactive Waste" will be published in the Federal Register on Friday, July 24, 1981.
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ENCLOSURE C
Meetings - Division of Fuel Cycle and Material Safety e---~
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Subj ecti ' '
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Miettiig with Conbustion Engineering'to discuss NRC.
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coments cn SNM License.1067 (Docket /0-1100) renewal application.
Date/ Time:
July 22 and 22, 1981 (all day meetings)
Place:
5th Floor Conference Room, SS Attendees:
H. Ketzlach, A. L. Soong, B. Kosla (FC), J.Roth (IE)
F. J. Pianki, G. A. Johnstone, G. J. Bakvich, (CE) 2.
Subject:
NUPAC, 60B Package Date/ Time:
8:30-11:30, July 23, 1981 Place:
5th Floor Conference Room, SS Atte. dees:
idegaarden and J. Fan (FC); D. Helsig (NUPAC) 3.
Subject:
Meating with staff of EPA regarding Memorandum of Understanding.
Date/ Time:
July 28, 1981, 9:00 a.m.
Place:
5th Floor Conference Room, SS Attendees:
R.E.Cunningham,R.G.Page.D.Mausshardt[NMSS)
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G. Cunningham, R. Fonner and F. Chanania (ELD)
J. Axelrad, et al (EPA) 4.
Subject:
Meeting with Deputy Director General Semenov of the IAEA to discuss IAEA and U.S. nuclear safety programs and issues.
Date/ Time:
2:30 p.m., July 28, 1981 Place:
Room 560, SS Attendees:
R. E. Cunningham, FC and DDG Semenov, IAEA 5.
Subject:
Meeting with General Electric Company of the United Kingdom to discuss Topical Report for Independent Spent Fuel Storage Installation Date/ Time:
July 29,1981, 9:00 a.m.
Place:
Room 450, SS Attendees:
L. C. Rouse and J. Roberts (FC), D. Reisenweaver (RES),
and David Wheeler (GE) 6.
Subject:
Meeting at Argonne National Laboratory' to discuss staff coments on the preliminary draft EIS for the Kerr-McGee West Chicago Site.
Date/ Place:
9:00 a.m., Chicago, Illinois, July 29 and 30, 1981 Attendees:
W. A. Nixon and E. Y. Shum (FC) and staff from Argonne National Laboratory.
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Subject:
Meeting to discuss proposed technical specifications for the GE-Morris Operation.
Date/ Time:
9:00 a.m., July 30, 1981 Place:
8th Floor Conference Room, SS Attendees:
T. Clark (FC) and C. C. Herrington, et al, GE ENCLOSURE C
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I Planned Meetings - Division of Safeguards L
Subject:
Meeting with NFS-Emin and representatives of LLL to assist-vulnerability assessment.
Date:
August 3-6, 1981 Location: Emin, Tennessec
- Attendees:
S. Frattali B. Mendelsohn, SG D. Joy, SG l
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OFFICE OF INSPECTION AND ENFORCEMENT Items of Interest-Week Ending July 24, 1981 1.
The following Prelimincy Notifications were dispatched during the week:
a.
PNO-I-81-81 Technical Operations, Burlington, Mass a Radiography Source.
r Reported Lost in Transit b.
PNO-I-81-82 National Bureau of Standards Reactor (DN 50-184) - Valve Malfunction Resulting in Draining Moderator c.
PNO-II-81-55 Turkey Point 4 - PressurizerSpray Valve Leakage Into Containment d.
PNO-II-81-56 Surry Unit No. 2 - Spurious Safety Injection and Reactor Trip e.
PNO-II-81-57 Brunsick Unit 2 -- Plant Shutdown Due to Main Steam Isolation Valve Failure f.
PNO-III-81-64 LaSalle County. Station - Structural Damage to Reactor Building Roof g.
PNO-IV-80-348 South Texas Project, Units 1 & 2 - Update-Expansion of Prey!ously Authorized Complex Concrete Placement h.
PN0-V-81-39A San Onofre Nuclear Generating Station, Unit No.1 - Gaseous Waste Decay Tank Failure from Apparent Hydrogen Ignition 1.
PNO-V-81-42 San Onofre Nuclear Generating Station, Unit No.1
- Gaseous Waste Decay Tank Failure from Apparent Hydrogren Ignition j.
PNS-V-81-07 Diablo Canyon, Unit 1 - Pre-Operational Physical Security Inspection Testing k.
Notice of Non-Routine Event Involving Agreement State or Agreement Materials 06 Analytic Inspection, Inc., Lafayette, Louisiana -
Offshore Radiography Incident 2.
The' following IE Circulars were issued:
a.
IE Circular 81-11. " Inadequate Decay Heat Removal During Reactor Shutdown", was issued on July 24, 1981, to all holders of B'.4R operating licenses or construction permits, b.
IE Circular 81-12. " Inadequate Periodic Test Procedure of PWR Protection System", was issued on July 22, 1981, to all nuclear power reactor facilities holding an operating license or a construction permit.
l ENCLOSURE D
3.
The following IE Infomaticn Notice was issued:
a.
IE Information Notice 81-21, " Potential '.oss of Direct Acce.cs to t
Ultimate Heat Sink", was issued on July 21, 1981, to all nuclear power rractor facilities holding in operating license or construction permit.
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e ENCLOSURE D
OFFICE OF.1UCLEAR P.EGULATORY RESEARCH IMPORTANT EVENTS FOR THE WEEK ENDING JULY 24, 1981 A.
Esperimental Programs Branen 1.
LOFT The containment vessel leak test conducted the first week in July has been reviewed by the DOE /ID safety staff and accepted. This fulfills the periodic testing requirement for demonstration of containment integrity.
Preparations are going smoothly for the July 30, 1981 scheduled L6-7/L9-2 simulation of the ANO-2 turbine trip and St. Lucie cooldown transients.
The tests will be witnessed b.y Mr. HeiDZ SeIDel. Director of Safety and Environmental Research of the West German Ministry for Science and Technolocie.
During the week of the test, Mr. Seipe) will be in Silver Spring. Maryland, to meet with Mr. Minogue for discussions about the LOFT program.
Hitachi has accepted the invitation of the Integral Systems Section to present results of their BWh integral systems facility tests at the Water Reactor Safety In onnation Meeting in October. A similar c
invitation was extended to ve Korean Advanced Energy Research Institute to participate in the meeting. They will be making presentations on heat transfer and flow stability criteria.
2.
PWR B0HT The final ORNL TLTF data tapes have been sent to the data bank at INEL. The following types of test data are avai,lable:
(a) bundle uncovery/ recovery (small break LOCA), (b) large break LOCA simulation, (c) transient film boiling, and (d) quasi steady state film boiling.
All of the ORNL THTF tests have been mounted at INEL except for the Series II Bundle Uncovery/ Recovery Tests.
These should be available to Data Bank Users by the and of this month.
3.
FLECHT SEASET Westinghouse successfully completed the last 21 rod blocked bundle test series. This bundle uses the exact blockage shape and configurations to be used in the 17 x 17 blocked bundle.
TFa test data is being qualified and significant findings will be reported at the Ninth Water Reactor Information Meeting in October.
ENCLOSURE E
y 4.
Semiscale The test NC-2 (Natural Convection) results show an increasing mass circulation rate with decreasing inventory which. reaches a maximum, and then decreases to approximately zero.
Reflux behavior initiated between 60 and 70 percent of original inventory (excluding the pressurizer).
Visual observations clearly show the reflux behavior, with about half of the water flowing out the cold leg side of the steam generator and half returning via the hot leg.
Tests NC-3 and -4, to obtain the effect of additional parameter variations, will be combined and are expected this week.
5.
Bi$_ Refill /Reflood 'Proaram Separate effects tests in the 30* Sector Steam Test Facility ($STF) have been completed and the first two systemt effects tests were successfully conducted. These latter tests tre simulation of the late blowdown and refill phase of a BWR LOCA.
Testing will continue through August when the facility will be reconfigured from a BWR/6 to a BWR/4 configuration.
6.
BWR FIST Design and scaling analyses continued. Major efforts include vessel design and evaluation of existing components for use in the upgraded facility. A significant question involves the jet pumps.
Current plans call for modifying the old TLTA jet pumps to correct the height scaling.
It is uncertain how the modifications will influence the jet pump performance.
GE is investigating possible perforrance testing of the modified pumps.
B.
Fuel Behavior Branch 1.
Lf1!
The test assembly for the clad ballooning test, MT-2, has been inserted in the NRU Reactor and in-pile check out of instrumentation has been initiated.
Fuel preconditioning is scheduled for July 22 and 23 and actual clad balloon-ing on July 23-24. New fuel transfer procedures should permit visual exam-ination of the test assembly dur ing the time of July 25-30. Test MT-2 is the second of a series of clad ballooning and rupture tests on an assembly of full-length, cgmmercial enrichment fuel reds. The target rupture temperature is 14000F-1500 F, a range where appreciable clad ballooning is expected at the relatively low anticipated clad heatup rate at rupture.
E23 ENCLOSURE E
9 Publications to be Issued in the Near Future
Title:
Standard Format and Content for the Safety Analysis Report for An Independent Spent Fuel Storage Installation (Dry Storage)
Expected Issuanc.e Date: September 1981
==
Description:==
Provides. guidance on the. content and format for the SAR for a Dry ISFSI.
It is the compliment of Reg. Guide 3.44
Contact:
D. Reisenweaver 443-5910
{
Publication Issued During the Week-oi July 20-24, 1981 Reg. Guide 3.47 - Nuclear Criticality Control' and Safety of Homogeneous Plutonium-ilranium Fuel Mixtures Outside Reactors-i r
4 I
i t
1-1 ENCLOS'JRE E l
ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING JULY 24, 1981 4
Chinese Rcaponse to Arrangement Proposal By cable dated July 22, IP was advised by the U.S. Embassy in Beijing that the State Scientific and Technical Commission of the People's Republic of China had responded to the cooperative arrangement proposal forwarded by NRC via diplomatic channels in December 1980 which J. D. Lafleur followed up with detailed discussions during a June 1981 visit to Peking.
As was indicated at the conclusion of these discussions, the Chinese have accepted most of the original proposal, with only a few relatively unimportant items remaining to be resolved. The primary divergence is their proposal to add a new item allowing for the assignment of Chinese special-ists to " participate in reseorch work on reactor safety in US institutions and universities and to prepare programs for accident analysis." They also wish to receive safety research reports on a routine basis.
IP will have to explore the feasibility of these suogestions with RES, ELD, and the Executive Branch before developing a response.
- ~ '
NEA Study: Safety of the Fuel Cycle The OECD Nuclear Energy Agency has published the " State-of-the-Art Report on Nuclear Fuel Cycle Safety" (CSIN/ SOAR No. 3), which had been under preparation for the last 21/2 years by a Working Group of the Committee on the Safety of Nuclear Installations. The report examines the safety of each individual stage of the fuel cycle, from uranium mining and milling to decommissioning. Particular emphasis is placed on accident analysis and on areas where further work would be desirable.
Certain aspects, such as radiation protection of workers, the release of radioactive effluents in normal operations, and the disposal of radioactive waste are not included in the review.
IP's copy of the report has been sent to the NRC Library where it may be requested from the Circulation Loan Desk, X28548.
Foreign Visits to NRC On Monday Dr. Lee of the Korean Advanced Energy Research Institute (KAERI) met with J. Lee and D. Powers, NRR, to discuss fuel rod bowing in Ko-Ri I.
On Tuesday Messrs. B. Favez, J. Mira, G. Simmonet and J. Stolz of Electricite de France (EdF) met with P. Collins and J. Cramer (NRR) and R. Di Salvo and J. Jenkins (RES), to discuss the training and licensing of operators and problems of human factors and related research.
On Wednesday G. Linsley of the U.K. National Radiological Protection Board met with E. Branagan and B. Richter (NRR), J. Martin and H. Peterson (RES) to discuss various environmental radiation questions.
On Thursday Perfessors Gharibba, Vacca and Ienco of the Italian Institute for Economy of Energy Sources met with H. R. Denton, NRR Director, to discuss the action now being taken to speed up the U.S. licensing process.
ENCLOSURE G
mwi OFFICE OF STATE PROGRAMS ITEMS OF INTEREST WEEK ENDING JULY 24',
1981 On July 21, 22 and 23, Bob Trojanowski, State Liaison Officer, Region II, participated in a Regional Assistance committee meeting in Thomasville, Ga.,The purpose of this meeting was to review the State of Florida Radiological Emergency Resr 'se plan to incorporate the plans for the local counties effe;
.J by operations at Turkey Point, St. Lucie and Crystal River nuclear' power plants.
On July 23 Mr. Trojanowski also met with Florida's designated NRC State Liaison Officer, Mr. Hamilton S. Owen, Jr., Adminis-trator, Power ' Plant Siting Section, Division of Environmental Regulation, to discuss low level waste disposal and other matters of mutual interest.
The California Health Department radiation control. program will be reviewed during the period July 27 - August 8, 1981.
NMSS' Materials Certification and Procedures Branch will'a'ssist.
SP and NMSS representatives met with Maryland Radiatica Control Program personnel to provide technical assistance to the State on the environmantal surveillance aspects of Neutron Products, Inc.
The meeting included a visit to t he NPI facility on July 21.
A representative of Oak Ridge Associated Universities, an NMSS contractor, was also present.
1 7,
ENCLOSURE H s.
I y
0FFICE OF MANAGEMENT N1D PROGRAM ANALYSIS Items of Interest WEEK EllDING JULY 24, 1981 Publications (1) Operating Unit Status Report (Gray Book), NUREG-0020, dated" June 1981; (2) SEP Status Summary Report, NUREG-0485, dated May 1981; and (3) Standards Development (Green Book),fiUREG-0566, dated June 1981, were fistributed.
e ENCLOSURE I
~ OFFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA ITEMS OF INTEREST WEEK ENDING JULY 24, 1981 Meeting with INP0 and NSAC On July 21, 1981, AE00 (Carl Michelson and Jack Heltemes) met with INP0 (Denr.is Wilkinson and others) and NSAC (Ed Zebroski) as an initial step in the implementation of the INP0/NSAC/NRC Memorandum of Agreement.
INP0 described their process.for receiving, reviewing, and disseminating infor-mation on operational events.
INP0 provided AE00 with copies of the 4-INP0/NSAC evaluation reports,18.Significant Operating Event Reports (50ERs),
and 101 of the 114 Significant Event Reports (SERs) issued to date. The
.emaining SERs are to be forwarded in t;1e near-future.
INP0 also discussea their LER trend analysis program using 17 "Special Interest Codes," and provided details on their 3 data files, i.e., reference documents, INPO internal records control, and technical information on individual plants.
The recent decisions regarding the shift of NSAC away from direct involvement in operational experience analysis, and the assumption by INP0 of the management and funding responsibilities for NPRDS were also discussed. Because of these shif ts in activities (effective January 1,1982), it was indicated that:
(a) the event evaluation program (SEE-IN) would be revised to cover only INPO activities; (b) prior to January 1,1982, a new Memorandum of Agreement should be developed to account for the new organizational responsibilities; (c) the funding for NPRDS will be borne by industry in CY 1982 and NRC funds will not be needed; and (d) AEOD reports should be sent to NSAC only for information.
The next coordination meeting has been tentatively established for mid-September in Washington.
ENCLOSURE K
fTEMS APPROVED BY THE COMMISSION - WEEK ENDING JULY 24, 1531 l
- A.
SECY-81-359 - TECHNICAL ASSISTANCE IN SUPPORT OF NRC REACTOR LICENSING. Memo SECY to Dircks, dtd 7/20/81.
This is to advise you that the Commission (with three-Commissioners approving) has granted approval for the staff to enter into the subject contract subject to the following conditions:
1.
Provide a report showing the specific tasks to be accomplished with definitions of the deliverables, the criteria under which acceptability of the deliverables will be judged, and the schedules for delivery.
This report should be submitted by October 1, 1981.
Subsequent reports should be provided each 6 months there-after, providing the accomplishments in that interval.
(NRR) 2.
The NRR Technical Assistance Task Force effort should be vigorously pursued.
3.
Careful attention should be given to the OIA report on this c~ontract and NRR priorities.
~
4 Periodic reports (no more frequent than once per quarter) sh'ould be submitted on the contribution of this and other NRR contracts to the Licensing Schedules of new plants and the backlog of licensing actions on operating plants. The first report should be submitted by September 1,1981.
(MPA)
Commissioner Ahearne disapproved the subject contract.
Attached are his dissenting comments. Although granting approval, the other Commissioners agree with these comments.
The Offices of Nuclear Reactor Regulation and Administration (Contracts) were informed of this action by telephone on July 17, 1981.
It is requested that you inform the Office of the Secretary when the contract is awar,deu.
Attachment:
As Stated leci ackdedl B.
SECY-81-390 - LICENSED FUEL FACILITY STATUS REPORT - VOLUME 1, NO. 6, JANUARY 1981 ISSUE.
Memo SECY to Dircks, dtd 7/21/81.
This is to advise you that the Commission (with all Commissioners approving) has approved the proposed report and authorized its release to the public.
I 1
ENCLG5UR3 M
~,.
,y e%.-
2 C.
SECY-81-397 - EXECUTIVE BRANCH RESPONSE Off PROPOSED EXPORT OF TRITIUM GAS TO ISRAEL, XB001130.
Memo SECY to Dircks, did 7/24/81.= ?
__.u This is to advise you that the Comission (with all Co.nissioners approving) has authorized the denial of the license to Milcor Corporation to export 30,000 curies of bulk tritium gas to Israel.
The Office of Inte.rnational Programs was informed of this action by telephone on July 24, 1981.
In connection with his approval, Comissioner Gilinsky posed the question:
"How many grams does this amount to?"
The staff has already informed him that it comprises approximately three grams.
It is requested that you forward to the Office of the Secretary a copy of the letter to Milcor Corporation after signature and dispatch by the Director, International Programs.
0.
SECY-81-400 - PROPOSED LICENSE TO EXPORT SOURCE MATERIAL TO ALL DESTINATIONS EXCEPT CUBA, KAMPUCHEA, NORTH KOREA, AND VIETNAM (XM08522).
Memo SECY to Dircks, dtd 7/24/81.
This is to advise you that the Commissioners have reviewed the subject license to Gerard Kluyskens Company, Inc.
The Commission (with four Commissioners approving) has accepted your recommendaten te export unlimitcd quantities of source material to all destinations except Cuba, Kampucl.n, North Korea and Vietnam comprising rare earth polishing compounds (primarly cerium oxide),
contaminated with small amounts of natural uranium and/or thorium in concen-trations ranging from 0.05 percent to 0.25 percent.
Co missioner Ahearne's approval is subject to making explicit the 500 kg/yr and 10,000 kg limit.
The staff of the Office of International Programs, which was infomed of this action by telephone on July 23, 1981, has indicated that this condition will appear in the license.
E.
SECY-81-232 - COMMENTS ON THE EPA PROPOSED FEDERAL RADIATION PROTECTION GUIDANCE FOR OCCUPATIONAL EXPOSURES.
Memo SECY to Dircks, dtd 7/24/81.
I This is to advise you that the Commission (with all Commissioners in agreement) has authorized dispatch of the comments to EPA concerning the proposed EPA guidance.
The Chairman signed and dispatched the letter forwarding the comments to the Administrator, EPA, on July 24, 1981.
-. ENCLOSURE.M
i 1 F.
SECY-81-398 - SECTION 208 REPORT TO THE CONGRESS ON ABNORMAL OCCURRENCES FOR JANUARY-MARCH 1981. - Memo SECY to Dircks, dtd 7/24/81. -
This is to advise you that the Commission (with all Commissioners approving) has approved the proposed report to the Congress, subject to the modiff tations to pages 4 and 5 as indicated on the attached sheet.
The Office of Anclysis and Evaluation of Operational Data was informed of this action by telephone on July 23, 1981.
It is requested that you forward the report, as modified in the attachment, and the forwarding letters to the Congress to the Office of the Secretary for signature by the Chairman (Suspense:
c.o.b. August 12,1981).
Attachemnt: DeT;cl ded G.
INTERIM HYDROGEN CONTROL RULE (SECY-81-245).
Memo SECY to Dircks, dtd 7/24/81.
The Ccmmission would like the revised Interim Hydrogen Control Rule by August 17, 1981.
The new rule should contain more definitive instruc-tions regarding analysis scenarios and equipment survivability, as was discussed in the last Commission meeting.
ENCLOSURE M