ML20058N392
| ML20058N392 | |
| Person / Time | |
|---|---|
| Issue date: | 02/12/1982 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| Shared Package | |
| ML20058M131 | List:
|
| References | |
| FOIA-92-436 SECY-82-075, SECY-82-75, WIR-820212-01, WIR-820212-1, NUDOCS 9310140235 | |
| Download: ML20058N392 (36) | |
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I UNITED STATES NUCLEAR' REGULATORY COMMISSION WASHINGTON, D. C. 2o555 INFORMATION REPORT sta-82->s rescoory 18, 1982 For:
The Commissioners From:
T. A. Rehm, Assistant for Operations Office of the EDO
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING FEBRUARY 12, 1982 A sumary of key events is included as a convenience to those Commissioners who may prefer a condensed version of this report.
Contents Enclosure Administration A
Nuclear Reactor Regulation B
Nuclear Material Safety and Safeguards C
Inspection and Enforcement D
Nuclear Regulatory Research E
P Executive Legal Director F
International Programs G
State Programs H
Management and Program Analysis I
Controller J
l Analysis and Evaluation of Operational Data K
f i I. I Small & Disadvantaged Business Utilization L*
l Regions M
Items Approved by the Comission N
e 9310140235 930218 GIbIN
-436 PDR Office of the Executive Director i
- No input this week.
for Operations Jj
Contact:
DIsrR3. CON:
T. A. Rehm, CEDO
% 4eed m s FOR INTERNAL NRC 49-27781 N ice 4~1 staff offices DISTRIBUTION ONLY g
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R. E. Ginna
- q ut The 11'cen'see ins'pected the ruptured 1ube in the steam generator
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9 l and discovered its exact location ahd the characteristics of
~ he rupture. The tube is.being plugged, and removal of.the tube tis not' anticipated due to its location in the tube bundle. Eddy y
current testing of the "B" steam generater has been completed.
Twenty other hot leg tubes are scheduled to.be plugged. However.
no p.ugging, other than the ruptured tube, is planned for the cold i
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The licensee is now diagnosing and repairing the two steam generators.
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l Testing to date projects that en the order of 8.000 to 10.000
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steam generator tubes may need. repair because of corrosion. GPU l
plans to remove the reactor vessel. head for inspection of the y
n reactor core internals.
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Diable Canyon _
y',
NRC issued a Notice of Violation to PG&E for a material false staterent related to the seismic reverification progre.m at Diablo Canyon.
1 Kerr McGee. West Chicaco NRC staff briefed Congressman Tom Corcoran of Illinois on decocnissioning plans for the site and other issues pertaining to the site.
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l 1.ow-1.evel Waste Comcacts_
The states belonging to the Southeast Interstate low-level Radioactive Waste Management Compact (except for ene) have introduced legislation into their respective legislative bodies. HRC will cocnent on their The Midwest Lew-level Radioactive Waste Comittee has j'
draft Ccmpact.
i reached a consensus en a draft compact and agreed to submit it to their respective state legislative coccittees for comment.
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ADMINISTRATION OF.THETREE00M 0F fMFORMATION ACT
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!$TATU$'0F REQUESTS a.. - '.,
4 I Initial"
"~. Appeal'of T
Recuest,
initial Decision r
.1 Received 125 5
i Granteds 56 0
~5 Denied 9
3 3
Pending 60 2
'Ax 1
ACTIONS THIS WEEK
[
Received Nancy C. Chapman.
Requests a copy of a comunication by W. J. Dircks j
Bechtc1 Power to N.,J. Palladino dated January 21,1982 regarding i
Corporation quality assurance changes.
(82-83)
Charles W. Elliott.
Requests.docume'nts relating to the running of any Thomas and Hair version of the Calculations of Reactor Accidents
't (82-84)
Consequences computer code for the Limerick 4
i Nuclear Gene ~ rating Facility and the running of 1
arty versteri:of, the MARCH, computer code for Limerick, f,
.i Sam E. Fowler.
Requests documents relating to allegations concerning
?
Fried. Frank. Harris.
Hayward Tyler Pump Company.
Shriver & Kampelr.an (82-85) 1 s
Reuben C. Ott.
Requests a copy of a petitten by knerican Potash and Dupont
.y Chemical. Company on March 6,1951 for the purpose
(
(82-86) of reinstating the rare earth exemption with other 3
unimportant quantities of source materials.
1 (HRC employee)
Requests four categories of information en himself.
(82-87)
Jean A. Estrada.
Requests ceptes of all invoices since 9/30/81 for i:-
h Professional Carpet carpet service in the D.C. Metro area under BPA 1
Service Nos. DR-82-C224 and DR-82-0225.
(82-88)
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1 CONTACT:
J. H. Felton T.
492-7211
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ENCLOSURE A
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2 Received, Cont'd (An individual requesting Requests all documents maintained by the NRC on information about himself) himsel f.
l (82-89)
(NRC employee)
Requests infont.ation regarding permanent part-time (82-90) positions in the NRC.
Nina Bell, Requests information on all nuclear projects which Coalition for have "mothbolled" or terminated and four categories Safe Power of documents regarding the Trojan Nuclear Power Plant.
(82-91 )
Steven C. Sholly, Recuests 24 listed documents regarding "TMI Action l
Union of Concerned Plan Steering Group Chronology."
Scientists i
(62-92) l l
Steven C. Sholly, Requests a copy of 24 listed documents regarding "The l
Union of Concerned Assessment of Nuclear Safety -- Programs of the Scientists Nuclear Regulatory Commission."
(82-93)
Douglas E. Lee, Ph.D.
Requests all documents regarding the radioactive (82-94) leak at the Robert E. Ginna Nuclear Power Plant.
MichaeT Alexancer Requests information on the Bonus Nuclear Power (B2-95)
Plant.
Malcolm H. Philips, Jr.,
Requests five categories of documents regarding the Debevoise & Liberman Proposed Rule on Interim Requirements Related to (82-96)
Hydrogen Control.
Steven C. Sholly, Requests a copy of SECY-82-35 concerning TMI-1.
Union of Concerned Scientists (82-97)
Granted Robert Nelson, In response to a request for four categories of Los Angeles Federation documents regarding disposal of radicactive wastes of Scientists by the Atomic Energy Project at UCLA, made available (82-10) over 1,000 pages.
ENCLOSURE A i
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Granted, Cont'd j
(An individual requesting In response to a request for documents maintained l
information about himself) in the NRC on himself, informed the requester the 4
(82-25)
NRC has no records pertaining to him in the NRC Systems of Records, NRC-11, 18, 27 and 39.
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(Individuals requesting In response to requests for information on their information about themselves)
Reactor Operator License exam results, made available (82-27 thru 82-29) the requested information.
l (Individuals requesting In response to requests for inforration on their l
information about themselves)
Reactor Operator License exam results, informed (82-30 thru 82-48) the requesters their examinations have not yet l
l been graded and that they will be provided with the requested records in March.
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Alyssa L. Talanker In response to a request for a list of names and l
1 (82-78) addresses of individuals and groups in Massachusetts l
who have submitted FOIA requests during 1981, l
made ava11eble the requested information.
Denied Michael D. Levi, In response to a request for documents discussing l
Critical Mass security problems and describing or recommending Energy Project emergency plans for test and research reactors, i
(81-486) made available 30 documents. Denied two documents in their entirety containing advice, opinions and recommendations of the staff. Denied portions of r
l one document containing unclassified safeguards l
information. Informed the requester additional l
documents subject to this request are already i
available at the PDR.
t Judith Schleicher, In response to a request for information concerning Township of the 1974 and 1976 incidents at Isomedix in Parsippany, Denville, New Jersey New Jersey, made available 16 documents. Denied (82-75) portions of four documents, the disclosure of which would constitute an unwarranted invasion of personal privacy.
i ENCLOSURE A f
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DIVISION OF CONTRACTS Week of February 12, 1982 PROPOSAL UNDER EVALUATION l
1.
RFP No. RS-NMS-82-032 Title - Borehole and Shaft Sealing Performance Criteria Description - The NRC seeks a thorough review of the subject of borehole and shaft seal performance and the identification of potential regulatory guidance and needed research. It is anticipated that the results of this study effort will be important to the development of technical directives and regulatory guides, review of site characterization and safety analysis reports, and the development of license review capabilities.
Period of Performance - Nineteen (19) months from date of contract award Sponsor - NMSS Status - Best and Final Offers due on February 12, 1982 CONTRACTS CLOSED OUT (All administrative action completed and final payment made)
CONTRACT NO.
CONTRACTOR CLOSE-0UT DATE N RC-02-77-201 -27 S. M. Stoller 2/8/82 N RC-02-77-201 -28 Ralph Stone & Company 2/8/82 NRC-02-77-201 -29 Leighten Associates 2/8/82 NRC-04-79-182 Kansas State University 2/9/82 NRC-05-77-385 State of Tennessee 2/9/82 NRC-05-77-008 Presearch, Incorporated 2/11/82 ENCLOSURE A t
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l OFFICE OF NUCLEAR REACTOR REGULATION
-WEEK ENDING FEBRUARY 12, 1982 l
l PRESSURIZED THERMAL SHOCK TO REACTOR PRESSURE VESSELS
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The Westinghouse Owners Group (WOG) has submitted its generic report, j
WCAP 10019 " Summary Report on Reactor Vessel Integrity for Westinghouse Operating Plants" and Combustion Engineering Owners Group (CEOG) has submitted its generic report, CEN-189 " Evaluation of Pressurized Thennal l
Shock Effects Oue to Small Break LOCAs with Loss of Feedwater for the Combustion Engineering NSSS." Also, we have received the 150 day responses from seven of the eignt licensees who received the August 21, 1981 NRC i
letter as follows:
e Robinson 2
-W e Turkey Point 4
-W e San Onofre 1
-W e Fort Calhoun
-CE e Maine Yankee
-CE e Calvert Cliffs 1 -CE o Oconee 1
-B&W Tne eichth licensee, General Public Utilities (GPU) indicates that its report on T!11-1 will be submitted by March 31, 1982.
I The WOG report concludes that a number of reactor vessels will require more plant specific evaluations and may require that remedial actions be l
implemented at some point in the vessel life to demonstrate vessel integrity to end of life. The licensees of the three Westinghouse reactors all concluded after making plant specific analyses that vessel integrity will be maintained to or beyond end of life.
The CEOG report concludes that all CE plants can withstand the postulated small break LOCA (SBLOCA) with extended less of Feedwater (LOFW) scenarios for the assumec life of the plant. The 150 day responses from the three licensees of i
operating CE plants all indicate that vessel integrity will be maintained for the lifetime of the plant.
The 150 day response from Duke Power Company concerning the Oconee 1 vessel concludes that no changes to the plant or additional fuel management, or reactor vessel annealing is necessary to assure safe operation of Oconee I through the design life of the plant.
Staff review of these reports is in progress.
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ENCLOSURE B
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R. E. GINNA I
The ruptured tube in the Ginna steam generator was inspected in May)1981.
I.
The ECT results showed that there was 20% penetration (an OD signal 3 to s
6 in. above the tubesheet. The failed tube is in row 42, column 55 which It is located in the " wedge is near the periphery of steam generator.This is the section of the support plates..
area" of the steam generator.
that does not have flow holes. Three of the six previous small leaks that have been experienced have been in that area. There is no sludge pile in that area.
The ruptured tube in the Ginna steam generator has been inspected using
~
2.
The rupture has been determined to start approximately 2 fiber optics.
to 3 inches above the tube sheet and is approximately 5 inches long.
The rupture is kite-shaped with a maximum width of 3/4 t6 7/8 inch.
RG&E postulates that the rupture was due to stress corrosion linked to differential expansion between the tube and the tube wrapper in the wedge region (a region where the tube support plate is fastened to the Profilometry, to determine bulging or unusual shape of the wrapper).
tubes, showed some bowing of the tubes in the area of the rupture, thus The ruptured tube is being plugged and adding credance to this theory.
removal of the tube is not anticipated due to its location in the tube bundl e. RG&E is planning to use fiber optics to inspect the ruptured tube from the secondary side.
Eddy current testing (ECT) of the "B" steam generator has been completed.
In addition to the ruptured tube, twenty other hot leg tubes are scheduled e
Three of the tubes are adjacent to the ruptured tube while j
to be plugged.
the others are tubes nonrelated to the accident that indicate intergranular attack (IEA) or >40% degradation. No plugging, other than the ruptured tube, RG&E has commited is planned for the cold leg of the "B" steam generator.
to ECT 100% of the "A" steam generator hot leg tubes plus all periphery tubes and a random sample of the sludge area tubes in the cold leg of the "A" steam l
generator.
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l ENCLOSURE B l
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- R. E. GINNA (Cont'd) 3.
Or Wednesday, February 10, 1982, members of the NRC staff met with epresentatives of Rochester Gas and Electric Corporation (RGAE) to discuss the requirements to be met prior to restart of the R. E. Ginna i
Nuclear Power Plant. RG&E had scheduled the startup of Ginna for Monday, February 15, 1982, and proposed operation until the scheduled May 15, 1982 refueling outage, at which time the plant would be shut down and eddy current tests (ECT) of the steam generators (S/G) would be performed. RG&E presented infomation on the cause and corrective action for the tube located in the wedge area that ruptured.
In addi-
' tion, there was a description of Power Operated Relief Yalve (PORV) modifications and discussion of emergency procedures.
5RGAE 'has performed extensive ECT of both S/Gs. The rup'tured tube has been inspected using fiber optic equipment and a videotape of the rupture was shown at the meeting. Fiber optic inspection of the secondary side of the "B" S/G is in progress. In addition.to the failed tube, the licensee has plugged 20 additional tubes in the "B" S/G because of inter-cranular attack or wastage indications.
The staff has' concluded that there was not sufficient technical basis i
presented at this time to pemit the Ginna plant to return to operation.
5pecifica11y, the staff felt that prior to restart RG&E should:
1.
Finish the fiber optic inspection of'the secondary side of "B" 5/G including inspection for loose parts; 2.
Obtain the S/G designer's opinion on the effects of plugging in the wedge area; and Prov' de a more complete basis for operating for the proposed 3 months.
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r A meeting to discuss the remaining areas will be set up when RG&E has l
l prepared their response.
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i ENCLOSURE B
., - -. =.., - -.
4 T-CEE MILE ISLAND. UNIT 1 (TMI-1) STEAM GENERATOR PROBLEM 1.
TMI Unit 1 is switching from preparations for restart to a. substantial job of diagnosing and repairing the two steam generators. Testing to date projects that on the order of 8,000 to 10,000 of the 31,000 steam generator tubes may need repair because of corrosion which has caused through wall cracks.
Part of their work will involve removing the reactor vessel head for inspection of the reactor core internals.
2.
GPU Nuclear (GPUNC) held a press conference today near TMI to discuss the status of and plans for correcting the corrosion problem with steam generator tubes. Most of the information which GPUNC discussed was previously '
reported. However, the following additional information was revealed at the press conference:
- GPUNC projects that on the order of 8,000 to 10,000 of the 31,000 steam generator tubes may require repair because of the corrosion.
- Because the corrosion is primary side induced, GPUNC presently plans to remove the reactor vessel head and at least partially defuel to I
facilitate inspection of vessel internals.
- GPUNC is evaluating the following repair methods:
. Plugging Tubes - This process would take approximately six months and l
the plant would restart at less than rated power.
. Plugging and Sleeving Tubes - A combination of plugging and sleeving
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might be used to avoid thermal / hydraulic problems and other problems related to block plugging and many tubes. This approach could take a year.
. Replacing All ' Tubes' or Replacing the Steam Generators - These approaches would probably take longer than a year and depend upon material availability and engineering requirements.
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1 ENCLOSURE B i
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NRC TMI PROGRAM OFFICE WEEKLY STATUS REPORT I
February 7,1982 - February 12, 1982 Plant Status Core Cooling Mode: Heat transfer from the reactor coolant system (RCS) l loops to reactor building ambient.
Available Core Cooling Modes: Decay heat removal systems.
Long tem j
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 removal (DHR) system.
Pajor Parameters (as of 0500, February 12,1982) (approximate values)-
Average Incore Thermocouples: 104 'F Maximum Incore Thermocouple:
135'F
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RCS Loop Temperatures :
-A B
Hot Leg 95'F 99'F t
Cold Leg (1) 76'F 82'F l
(2) 79'F 88'F l
RCS Pressure: 96 psig Reactor Building: Temperature:
62'F Water level:
Elevation 284.1 ft. (1.6 ft. from floor)
Pressure:
-0.34 psig Airborne Radionuclide Concentrations:
1.8 E-6 uCi/cc H3 (sample taken 2/8/82) 5.5 E-6 uti/cc KrB5 (sample taken 2/9/82)
Effluent and Environmental (Radiolacical) Information 1.
Liquid effluents from the TMI site released to the Susquehanna River after processing, were made within the regulatory limits and in accordance with NRC requirements and City of Lancaster Agreement dated February 27, 1980.
During the period February 5,1982, through February 10,1982, the effluents contained no detectable radioactivity at the discharge point although individual effluent sources which originated 1
within Unit 2 contained minute amounts of radioactivity.
Calculations indicate that less than one ten-millionth (0.0000001) of a curie of cesium was discharged.
ENCLOSURE B i
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Airborne Effluents. Airborne effluents released to the environment were witnin the regulatory limits and in accordance with NRC requirements.
The licensee reported the following gaseous releases:
November December Unit 11_
EPICOR II Urd t Il__
EPICOR II Noble Gases (C1) 5.82 5.34 24.4 7.39 Particulates (Ci) 1.01 E-6 4.17 E-5 1.14 E-5 1.56 E-7 Tritium (Ci) 13.0 1.2 E-2 1.14 3.1 E-2 The above releases represent a small fraction of the allowable regulatory limits. These quantities are consistent with previous releases associated with routine operations.
Instantaneous airborne effluents are measured on a continuous basis, however, for accurate calculation of total curies released, effluent samples are analyzed in the laboratory and the resulting data evaluated and tabulated.
3.
Environmental Protection Acency (EPA) Environmental Data.
The EPA Middletown Office has not received the analytical results for Kr-85 measurements around the TMI site from the EPA's Counting Laboratory at Las Vegas, Nevada. When these results become available, they will be included in a subsequent report.
No radiation above normally occurring background levels was detected in any of the samples collected from EPA's air and gamma rate networks during the period from February 3,1982 through February 11, 1982.
4 NRC Environmental Data.
Results from NRC monitoring of the environment i
around tne TM1 site were as follows :
The following are the NRC air sample analytical results for the onsite continuous air sampler:
1-1 31 Cs-137 Sample Period (uCi/cc) _(uCi /cc)
HP-306 February 3,1982 - February 10, 1982
<6.2 E-14 <6.2 E-14 5.
License Radioactive Material Radwaste Shioments.
On Monday, February 8,1982, a one liter liquid sample from the Unit 1 " A" decay heat removal system was mailed to Babcock and Wilcox (B&W), Lynchburg, Virginiti.
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ENCLOSURE B I
On Wednesday, February 10, 1982, a one liter liquid sample from the Unit 1 waste evaporator and a one liter liquid sample from the " A" waste evaporator condensate storage tank were sent to the Radiation Management Corporation, Philadelphia, Pennsylvania.
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On Wednesday, February 10,1982, a 250 m1 liquid sample from j
the Unit 1 " A" decay heat removal system was sent to Vermont l
Yankee, Vernon, Vemont.
On Wednesday, February 10, 1982, 96 surface samples from the Unit 2 reactor building were sent to EG & G. Scoville Idaho.
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6.
TMI Occupational Exposure _, Licensee TLD (Themoluminescent Dosimeter) recorcs indicate tne following Unit 2 total occupational radiation j
exposure for 1981:
December 1981 21 man-rem
- Total 1981 (January-December) 147 man-rem I
- Man-rem is an expression fcr the summation of whole body doses to individuals in a group.
Thus, if each member of a population l
group of 1,000 people were to receive a dose of 0.001 rem (1 millirem),
or if two people were to receive a dose of 0.5 rem (500 millirem) i each, the total man-rem dose in each case would be one man-rem.-
b Major Activities 1.
Submerced Demineralizer System (SDS).
Transfer of approximately i
l 20,000 gallons of water (baten 19) from the reactor building was perfomed on February 7,1982.
On February 7, processing of batch 19 commenced. On February 9, processing of batch 19 was terminated because of a malfunctioning sample valve.
Transfer of batch 20 (32,000 gallons) from the reactor building sump commenced on l
February 9 and completed on February 10. The SDS was restarted on February 11, 1982.
To date approximately 540,000 gallons of water t
has been transferred from the reactor building sump. SDS performance I
parameters for batch 19 ere enclosed.
2.
EPICOR II. The EPICOR II system continued to process SDS effluents ouring tne report period. Perfomance parameters are enclosed.
3.
Reactor Buildino Entries _. There have been no entries into the reactor Duiloing (PS) since February 4,1982. The next entries are scheduled for February 16 and 17,1982. Major tasks planned for the next two entries include the following:
Installation of new fire hoses Power lift installation / load test (device to transit to the polar crane)
Portable, gamma spectrometer survey of the 347 ft. elevation Installation of decon hoses through penetration R-561 j
E! CLOSURE B f
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4 Tritium Increase In Ground Water Samples. Tritium levels in water f
samples from several test oorings (test borings 2,16 and 17) in l
the vicinity of the bora*.ed water storage tank (BWST) have increased substantially in February. The licensee has subsequently increased the sampling frequency to daily sampling of all test borings. The NRC has obtained a ground water sample for independent analysis, and has also contacted EPA to perform a second independent analysis, j
The tritium levels detected to date are below the maximum pemissible l
concentration (MPC) for unrestricted areas and pose no hazard to workers or the general public.
It is suspected that the increase in ground water activity resulted from a leak of BWST water on January 13,1982 (see Weekly Status Report dated January 18, 1982).
The estimated 50 gallons of leakage contained the following isotopes:
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H3 1.1 x 10-1 uti/mi Sr90 2.9 x 10-6 uti/ml
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Csl34 1.6 x 10-4 uCi/mi l
Csl37 3.6 10-4 uti/mi Since soil absorbs and slows the migration of these nuclides to varying degrees, the potential for detection of these nuclides in l
future well samples exists. It is expected that samples taken in the future may contain these nuclides.
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l ENCLOSURE B
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Chairman Palladino Visit to THI On Tuesday, February 23, 1982, NRC Chairman Nunzio Palladino is scheduled to come to Three Mile Island to meet with the NRC staff and review i
activities at the site.
It is expected that a short press conference for the news media will be held at the NRC Middletown Office following his visit.
i Future Meetings 1
1.
On Friday, February 19, 1982, Lake Barrett will meet with the l
Middletown Mothers to discuss TMI related issues in general.
2.
On Friday, February 26, 1982, Lake Barrett will be speaking for the dinner meeting being held by the Engineers Week Joint Planning l
Council to honor Lehigh Valley's Engineer of the Year and Young l
Engineer of the Year.
3.
On Saturday, March 13, 1982 Lake Barrett will address the Society of Manufacturing Engineers in Williamsport, PA, on the cleanup of l
TMI and general aspects of nuclear power.
i ENCLOSURE B r
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i l-i l-ATTACHMENT 1 SDS Performance for Batch Number 19 Average Average Average Radionuclide Influent Ef fluent DF l
luc /ml)
(ut/ml) f 5
Cesium 137 1.2 x 102 5.4 x 10-4 2.1 x 10 Strontium 90 4.8 6.4 x 10-3 7.5 x 102 EPICOR 11 Performance February 2.1982 to February 6.1982 Average Average Average Radionucli de Influent Ef fluent DF (uc/ml)
(uc/ml)
Cesium 137 6.6 x 10-4 2.4 x 10-7 2.8 x 103 Strontium 90 9.6 x 10-3 5.8 x 10-6 1.3 x 103 Antimony 125 1.1 x 10-2
<4.1 x 10-7
>2.7 x 104 l
ENCLOSURE B t
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L OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending February 12, 1982 Briefing of Congressman Corcoran on Kerr-McGee West Chicaao On February 8,1982, Congressman Tom Corcoran of Illinois was briefed at his request, regarding the decommissioning plans for the Kerr-McGee West Chicago plant site, NRC licensing actions pertaining to the site and the adjacent Kress Creek and the thorium ground contamination at various locations in the city of West Chicago.
The following subjects were discussed in the meeting:
1.
The history of the Kerr-McGee West Chicago facility.
2.
The application by Kerr-McGee to decommission the facility.
3.
The EIS on the Kerr-McGee Decommissioning Plan and alternatives to the plan which will serve as a basis for licensing decisions.
4.
The EIS schedule, i.e., publish draft in April or May 1982, receive comments and publish final EIS later in 1982.
5.
The areas contaminated with thorium in West Chicago that resulted from activities which occurred before Federal Government licensing authority was established and over which NRC has no legal authority.
6.
The NRC letter to Kerr-McGee requesting that the company submit a plan for the cleanup of Kress Creek.
l 7.
NRC attempts to get EPA to sign a Memorandum of Understanding to define generally the responsibilities of each agency for contaminated sites.
CRBR Fuel Cycle Environmental Review A meeting was held on February 3,1982, between representatives of DOE, NRR, and NMSS to discuss the type of information that DOE should include in their en-vironmental report to facilitate NRC's independent review. The DOE representa-tives agreed to provide additional safeguards naterial as soon as possible so that the CRBR fuel cycle review process can proceed expeditiously.
t LEU Reform Amendments A working draft regulatory amendment for MC&A requirements on low enriched uranium (LEU) facilities has been distributed for internal NRC staff comment.
The purpose of the amendments is to make MC&A requirements commensurate with the low strategic significance of LEU. The working draft contains changes in cur-rent 10 CFR 70.51 requirements for LEU facilities and asks for staff views on possible changes to 10 CFR 70.57 and 70.58 requirements.
ENCLOSURE C l
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4 Meetines - Division of Fuel Cycle and Material Safety 1.
Subject:
To discuss General Electric's renewal and incinerator license applications and discuss environmental matters with General Electric and the State.
Date/ Time:
February 16-19 Location:
Wilmington, North Carolina Attendees:
E. Y. Shum (FC), G. H. Bidinger (FC),
R. L. O'Connell (FC), Representatives fmm General Electric, State Representatives 2.
Subject:
To meet with the major companies involved in flooding studies for gas and oil recovery using radioactive tracers.
Date/ Time:
February 17-18 Location:
Houston, Texas Attendees:
T. F. Carter (FC), B. Singer (FC), J. M. Brown (FC),
Representatives from Industry, Representatives from State 3.
Subject:
Type A shipping casks.
Date/ Time:
February 18 - 1:00-3:00pm Location:
Willste - 5th floor conference room Attendees:
R. Odegaarden (FC), H. Lee (FC),
Repntsentative from Washington Public Power Supply System 4.
Subject:
Meeting with Steven Kraft of Edi. son Electric to discuss GESMO.
Date/ Time:
February 10 - 9:00am Location:
Room 562, Willste Building Attendees:
R. E. Cunningham (FC), H. Lowenberg (FC),
Steven Kraft (Edison Electric) 5.
Subject:
Pre meetings and meeting of NEA Committee on Radiation Protection and Public Health.
Date/ Time:
February 19-27 Location:
Paris, France Attendees:
R. E. Cunningham (FC). NEA members Meetines - Division of Waste Manacement 1.
Subject:
Discussion and clarification of a Series of Issues Related to the State of New Mexico's Preliminary Request for an Amended Agreement with the NRC Date/ Time:
February 16, 1982 Location:
Santa Fe, New Mexico Attendees:
Don Nussbaumer, John Kendig (OSP); Robert Fonner (OELD);
Ross Scarano and Kathleen Hamill (NMSS/WMUR)
ENCLOSURE C 1
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Division of Safeguards - Planned Meetings 1
Subject:
To discuss Brookhaven Lab's capabilities Date:
February 25, 1982 Place:
Willste - 8th Floor Conference Room Attendees: Representatives from Brookhaven R. F. Burnett & representatives from SG l
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O 0FFICE OF INSPECTION AND ENFORCEMENT ITEMS OF INTEREST February 8,1982 to February 12, 1982 1.
Significant Enforcement Action - On February 11, 1982, a Notice of Violation was issued by IE to the Pacific Gas and Electric Company for a material false statement related to the Seismic reverification program at the Diablo Canyon Nuclear Power Plant. The letter transmitting the Notice of Violation provides that a meeting will be held with the Director of IE, the Administrator of Region V and the Chairman of the Board of the Pacific Gas and Electric Company.
2.
Preliminary Notifications relating to the following actions were dis-patched during the week:
a.
PNO-I-82-16, Niagara Mohawk Power Corporation (Nine Mile Point - Unit 1) -
Overflow of Sludge Tank Containing Radioactive Water.
b.
PNO-II-82-17 Duke Power Company (Oconee Unit 1) - Steam Generator Tube Leak.
c.
PNO-II-82-18, Virginia Electric and Power Company (Surry Unit 1) -
Reactor Trip and Safety Injection.
d.
PNO-II-82-19, Georgia Power Company (Hatch Unit 1) - Radwaste Processing System Overflow.
e.
PNO-III-82-16A, Consumers Power Company (Palisades) - Hydrogen Leak on Main Generator, Explosion, Fire, and Personnel Injury, Update.
f.
PNO-III-82-17, Wisconsin Electric Power Company (Point Beach Unit 1) -
Unit Shutdown to Repair Minor Leak, g.
PNO-III-82-18. Commonwealth Edison Company (Zion) - Suspension of Two Guard Force Members.
h.
PNO-III-82-19, Commonwealth Edison Company (Zion Unit 2) - High Turbine Vibration.
- i. PNG-III-82-20, U. 5. Ecology (Sheffield, Illinois) - Detection of Tritium in Offsite Ground Water Samples at the Sheffield Low Level Waste Burial Site.
l 3.
IE Information Notice No. 80-32, Revision 1: Clarification of Certain Requirements for Exclusive-Use Shipments of Radioactive Materials was forwarded to the Regions for issuance on February 12, 1982 to all fuel facility, materials, and Part 50 licensees.
ENCLOSURE D 1
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4.
Other Items a.
On February 12, 1982, the Director of IE and the Regional Administrator of Region III will inspect the quality assurance program at the Marble Hill reactor facility.
i b.
The Director of Division of Emergency Preparedness participated in a meeting with INPO on February 9,1982 to discuss NRC regulations 10CFR50.72 and 50.73.
c.
The Enforcement Staff met with representatives of' Cincinnati i
Gas and Electric Company on February ll, 1982 to discuss the quality assurance deficiencies alleged in the civil penalty action taken against Zimmer on November 28, 1981.
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ENCLOSURE D i
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OFFICE OF.fuCLEAR REGULATORY RESEARCH ItlPORTANT EVENTS FOR THE WEEK ENDING FEBRUARY 12, 1982 l
Severe Accident Assessment Branch 1.
Three-dimensional Thermal Hydraulic Calculations - ANL l
A report "C0tNIX-1 A Three-Dimensional In-Vessel Simulation of the FFTF l
Thermal Hydraulics" by S. P. Vanka et. al. of AHL NUREG/CR-2535, ANL-CT-82-1 has been issued. The report gives results of a complete invessel calculation of FFTF temperature and flow distributions at full power steady state condi-tions. Agreement with temperature and flow measurementg is generally good.
The calculation shows a large temperature gradient (140 C/Ft.) under the outlet nozzel. No instrumentation is in a location to measure the gradient.
Similar calculations are in progress for CRBR.
2.
HRC/EPRI Hydrocen Research Review Meetino A joint NRC/EPRI Hydrogen Research Review Meeting was held in Dallas on February 3-4, 1982. The meeting provided a review and status of hydrogen related safety research being sponsored by both the NRC ed EPRI. In addi-i tion to the participants from the two sponsoring groups, representatives were in attendance from several utilities, the Department of Energy and the industry's IDCOR program. The research discussed included work on hydrogen combustion limits, hydrogen control and mitigation studies, combustion and transport model development, flame acceleration studies md hydrogen burn equipment survival research. The meeting focused on current results, inter-pretation of results and perceived needs for future work. The NRC and EPRI have tentatively agreed to jointly host the 2nd International Workshop on l
Hydrogen Safety for Light Water Reactors in October 1982-Analytical Models Branch 1.
A meeting was held with ORNL personnel to discuss the definition of Pressurized Thermal Shock (PTS) accident scenarios for the chosen i
B&W plant. Two or three of the bounding cases will be ch:tsen before l
the end of February for calculation by RES/DAE contractors. One of the cases already analyzed by the utility will also be chosen.
I 2.
A 2-day Advanced Code Review Group meeting on the Thermal-Hydraulics of PTS is being planned for the middle of April, 1982. EPPJ and its.
contractors will be invited. RES/DAE contractors will mest in Silver Spring on March 3,1982, right after the March 2,1982 visit to. Duke Power, to discuss the status of calculations and plan for the April meeting.
3.
Marviken critical flow reports are now declassified and rrangements are being made for their efficient distribution.
4 J. Han completed a two-week PWR Systems Training Course t Chattanooga..
ENCLOSURE E i
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- t Exoerimental Procrams Branch 1.
Data Bank Two new Semiscale Natural Circulation Tests were added to the data bank: S-NC-4B and S-NC-05. Also, a 6 Percent Small Break Semiscale Test, S-UT-8, was entered in preliminary form and is password protected.,
Data from Simulated Core Boiloff Experiment 5005 from the Swiss NEPTUN facility were added to the bank.
l 2.
BWD. Full Intecral Simulation Tests (FIST)
A Program Management Group (PMG) meeting is scheduled for March 1-2, 1982 in San Jose. A review of program progress to date and discussions
~
of the Phase 11 proposal are the major planned agenda items.
i 3.
BWR Refill /Reflood Program Problems with coordination of the GE contributions to the BWR TRAC effort at INEL have recently been identified. INEL staff will meet with GE staff the week of February 16, 1982 to clarify the problems and propose solutions. A PMG meeting will'be held on March 3,1982 in San Jose to review the problem and the proposed solutions.
l 4.
Correlation Evaluation Received responses from France concerning the Correlation Evaluation Two sets of film boiling data obtained at Chalk River l
program.
were referenced. Additional data was also enclosed.
5.
Semiscale The third test in, the S-IB series, a 50 percent cold leg break, is anticipated on Wednesday, February 10, 1982. Processing of data from the 100 percent and the infomal 200 percent cold leg break tests is continuing.
Work is being initiated on the 2 X 4 PWR configuration integral test investigation (MOD 5).
Final planning for a series of meetings to be held jn Bethesda,"
is in progress. Thefollowinghavebeenschedu{ed:.
March B: RELAP5 Users, emphasis on NRR needs;).
' March 9: Semiscale Review Group; ENCLOSURE E l
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. Experimental Programs Branch March 10: Discussion of test planning, including M005 pressurizer behavior, candy cane behavior, cold leg downcomer therral mixing (EPRI), and Semiscale feed / steam line break j
series; and March 11: Semiscale Mid-Year Review.
Fuel Behavior Branch 1.
NRU FBB and its contractor PNL, presented an extensive summary of recent NRU clad ballooning test results and future test plans to representatives l
of various interested groups, including UK, JRC-Ispra, JAERI, EPRI, AECL, W, GE, CE, EG&G, ORNL, MIT, Univ. of MD, and NRC/RES and NRC/NRR. Test observers have already begun using the NRU test data for evaluating clad ballooning and flow blockage computer models and correlations based on i
non-nuclear (out of pile) test data. After the presentations UK repre-sentatives examined continuing UK financial support of FBB programs based i
on the perceived effectiveness of the FBB-NRU test program and the expected effectiveness of companion FBB test programs.
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! l, Publications to be Issued in the Hear Future
}
Title:
Guidelines for Germanium Spectroscopy Systems for Measurement of Special Nuclear Material (Draft Regulatory Guide 5.9, Rev. 2)
==
Description:==
This guide is being revised to reflect improvement in f
tecnniques and to bring the language of the guide into conformity with current usage.
l
Contact:
S. Frattali 443-5976 j
r
Title:
Nondestructive Uranium 235 Enrichment Assay by Gamma-Ray Spectrometry (Draft Regulatory Guide 5.21 Rev. 1)
Descriotion: This guide is being revised to reflect improvements in technique l
anc to bring the language of the guide into conformity with current usage.
Contact:
S. Frattali 1
443-5976 1
Title:
Nondestructive Assay for Plutonium in Scrap Material by Spontaneous Fission Detection (Draft Regulatory Guide 5.34, Rev. 1)
==
Description:==
This guide is being revised to reflect improvement in techniques and to bring the language of the guide into conformity with current usage.
Contact:
S. Frattali 443-5976 l
5
Title:
Qualification Calibration, and Error Estimation Methods for Nondestructive Assay (Draft Regulatory Guide 5.53, Rev.1)
[
==
Description:==
This guide is being revisea to reflect improvements in techniques and to bring the language of this guide into conformity with current usage.
Contact:
S. Frattali l
443-5976 r
b ENCLOSURE E
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Title:
Physical Protection for Transient Shipments
==
Description:==
This guide describes measures acceptable to the NRC staff i
that can be taken by the licensee to provide the physical protection for scheduled and unscheduled transient shipments required by 10 CFR Part 70.
l
Contact:
Kris Markulis 443-5976
Title:
Emergency Plannin for Research and Test Reactors (Draft Regulatory Guide 2.6, Rev. 1
==
Description:==
Established emergency preparedness requirements for research and test reactors. Endorses ANSI /ANS 15-16,
Contact:
M. Jamgochian 443-5942 I
Publications Issued During the Week of February 8-12, 1982 f
Reg. Guide 3.1, Rev.1 - Use of Borosilicate-Glass Raschig Rings as a Neutron Absorber in Solutions of Fissile Material ENCLOSURE E f
OFFICE OF THE EXECUTIVE LEGAL DIRECTOR ITEMS OF INTEREST WEEK ENDING FEBRUARY 12, 1982 t
l Diablo Canyon Nuclear Power Plant, Units 1 and 2 l
i On February 10, 1982, the Commission issued a Statement (CLI-82-1) in which t
it directed the NRC staff to issue a Notice of Violation with regard to l
statements made by representatives of the Pacific Gas and Electric Company j
relating to PG&E's review of a report prepared by its consultant R. L. Cloud Assoc., Inc. addressing the ongoing seismic reverification program for l
Diablo Canyon.
Commissioners Ahearne and Roberts dissented.
1 West Chicaoo Rare Earth Facility On February 11, 1982, the Commission issued an Order (CLI-82-2) in which it rejected four petitions filed by the City of West Chicago for a hearing on.
l a request by the Kerr-McGee Corporation for an amendment to its Part 40 j
license for the thorium ore milling facility located in West Chicago, Illinois.
l The amendment permits the demolition of certain buildings and the receipt and
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1 storage of a small quantity of mill tailings. Commissioners Gilinsky and l
Bradford dissented from the Order, i
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ENCLOSURE F l
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i ITEMS OF INTE'4EST l
OFFICE OF INTERNATIONAL PROGRAMS l
WEEK ENDING FEBRUARY 12, 1982 8
Foreign Operator Qualification Survey j
IP has now received the last of the foreign comments on, and changes to, the f
draft report on foreign operator qualification and training which was prepared j
by RES from information supplied last year by the 17 Western Bloc countries i
with operating, or soon to be operating, power reactors and Taiwan. We will l
see that all participants receive copies of the report, along with a letter of thanks, as soon as it is published.
j Meeting With Yugoslav Representative at the Commerce Department f
^
On Monday representatives from the Department of State, Energy. Commerce, NRC.
i TVA, G.E., Westinghouse, Combustion Engineering and the ANS met with Milan l
Pavicevic, Secretary to the Federal Executive Council of the Yugoslavian Nuclear Energy Commission, to discuss the proposed visit to the U.S., in May l
l of a senior level nuclear energy delegation.
Prior to the delegation's U.S.
l l
visit, the ANS has agreed to co-host a seminar in Yugoslavia on the status of nuclear energy in the U.S.A.
Foreign Visits to NRC On Tuesday a Yugoslav delegation headed by Zvone Dragan, Vice President of the Federal Executive Council (Cabinet) of Yugoslavia, met with all five Cornissione'rs and J. La'f16ur of IP to discuss _, Yugoslavia's nuclear power program.
l On Thursday Mr. Lars G. Larsson, Director of the Office of Inspection of the Swedish Nuclear Inspectorate (SKI), participated in the NRC observation of the emergency preparedness exercise at the St. Lucie nuclear plant.
Mr. Larsson j
is one of several foreign regulatory personnel with immediate responsibility l
for emergency preparedness activities in their own countries who are being l
selectively scheduled to participate as a part of the NRC observation team j
in emergency preparedness exercises at U.S. facilities.
ENCLOSURE G I
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- Foreion Reports The following foreign reports were received in IP February 8-12:
j (For further information contact Eva Szent-Ivany, IP, X27788.)
l From France:
Planning of Construction: October 1981 From Israel:
Updated list of documents (attached) from Israel, each of which can be l
made available upon request.**
i From Italy:
CNEN-RT/ DISP (81)6 - Radioactive Releases from Nuclear Power Plants:
Status and Perspectives. Part I: Boiling Water Reactors t
I CNEN-RT/ DISP (81)7 - The Consolidation of Unsaturated Soil l
CNEN-RT/ PROT (81)15 - Electrochemical Etching I - Mechanism **
CNEN-RT/ PROT (81)18 - Electrochemical Etching II - Methods, Apparatus and Results**
CNEN-RT/ PROT (81)19 - Lyoluminescence Measurements of Mannose and Glucose
)
1 CNEN-RT/ PROT (81)20 - Determination of Low Levels of Plutonium in Biological and Environmental Samples by the Fission Tracks Technique CNEN-RT/ PROT (81)22 - The Characteristics and Requisites of Ionizing Radiation, Based on Operational Experience in Radioprotection in j
Nuclear Power Plants i
Deleted from PDR copy
- Indicates the reports are in English l
4 ENCLOSURE G t
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~...,-,,-.,
r Report No.
Title Author Date LDI-81-37 Ultinate Heat Sink for Nuclear E. Zell April 1981 Power Plants.
D. Ilberg (Hebrew), 49 pages Y. Hertz A. Weissman LDI-81-38 Synthesis-Synthetic Acceleration Z. Shayer July 1981 Method as Applied to the Diffusion Equation, 29 pages LDI-81-39 Postulated Transport of Radio-A. Ra=ati July 1981 nuclides by Fog and Dew in an Arid Ecosystem, 12 pages LDI-81-40 The Vulnerability of Engineered Y. Hertz July 1981 Safety Auxiliary Power to an D. Ilberg External Event - Presented to ANS/ ENS Prebabilistic Risk Assess =ent Meeting. Port Chester N.Y., Sept /81, 8 pages LDI-81-41 Apparent Annual Probability of A. Shapira Aug. 1981 Exceeding Peak Ground Acceleration, 23 pages-LDI-81-42 A Progra= for Bidirectional Data M. Stark Oct. 1981 Transfer Between Wang and C.D.C Computers using the "Intercome" Protocol (Hebrew), 25 pages L01-81-43 Fire Barriers in Nuclear Power A. Weissman March 1981 Plants (Hebrew), 73 pages A. Dayan D. Ilberg ENCLOSURE G i
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2 0FFICE OF STATE PROGRAMS, ITEMS OF INTEREST WEEK ENDING FEBRUARY 12, 1982 I
All except one of the initially eligible party States to the Southeast Interstate Low-Level Radioactive Waste Management Compact have introduced legislation into their respective legislative bodies. These States are Alabama, Florida, Georgia, Mississippi, South Carolina and Tennessee.
North Carolina is the single exception. The Georgia House passed the compact bill unanimously on February 10, 1982. Virginia introduced into their legislature a bill to enact and enter into the Southeast compact.
Virginia is not listed among the " initially eligible parties" in the current draft of this compact. NRC has been asked by the Southern States Energy Board to comment on the draft (January 20, 1982) Southeast Interstate Low-Level Radioactive Waste Management Compact on behalf of the eligible party States.
l William B. Menczer, Regional State Liaison Officer, Region III, on February 9, l
1982 was in Rosemont, Illinois meeting with the Midwest Low-Level Radioactive l
Waste Connittee. The States of Michigan, Ohio Wisconsin, Indiana, Maryland, Virginia, Delaware, Minnesota, Illinois, Kentucky, Nebraska and Iowa partici-pated. The Committee reviewed and reached consensus on the-draft compact and agreed to submit it to their respective State legislative committees for comment and identification of conflicts with State constitutions and existing State legislation. The Committee will reconvene in July,1982 to incorporate final changes and to vote on a final document for State legislative enactment.
William C. Taylor, advisor to Governor Milliken, Michigan, formally requested that NRC comment on the draft (January 11,1982) Midwest Interstate Low-Level Radioactive Waste Compact on behalf of the 16 eligible party States --
Delaware, Illinois, Indiana, Iowa, Kansas, Kentucky, Maryland, Michigan, Minnesota, Missouri, Nebraska, North Dakota, Ohio, South Dakota, Virginia, and Wisconsin.
l The draft is currently being reviewed by several NRC offices.
i ENCLOSURE H I
i OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS Items of Interest WEEK ENDING FEBRUARY 12, 1982 i
Chairman's Trip l
Drafted speech and prepared background paper for l
Chairman Palladino's trip to Casper to address the Wyoming Energy Conference.
l l
Publications Issued NUREG-0020. " Licensed Operating Reactors Report" (Gray Book) Vol. 5. No. 11, and updated " Generic Items Tracking l
System Report."
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l Office of the Controller Items of Interest Week Ending February 12, 1982 Publication of NRC Debt Collection Procedures as a Final Rule in the Federal Register On February 8, 1982, the Executive Director for Operations approved for publication and signed a Federal Reoister notice amending its regulations by adding a new Part which establishes the procedures that NRC will follow to collect debts which are owed to it except for civil monetary penalties for violation of a licensing requirement. The procedures are based upon the Federal Claims Collection Standards issued by the General Accounting Office and the U. S. Department of Justice, as amended on July 31, 1981. The Federal Claims Collection Act of 1966 provides that these procedures be issued as regulations. The procedures will enable the NRC to improve its collection of debts. The preamble to the rule contains a statement that the Comission certifies that the rule does not have a significant economic impact on a substantial number of small entities; interest and late payment charges imposed on a small entity will ordinarily not exceed $100 per year. On September 23, 1981, the NRC published a proposed rule in the Federal Register inviting comments for 45 days ending November 9,1981. Appropriate changes were made l
in response to two comments received. The first comment sought to restrict l
the suspension or revocation of a license for non-payment of a debt to the single license involved. The second comment sought to have the rule impose late payment charges only on debts initially asserted after the effective date of the rule.
Budcet Hearine procram Statement I
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Prepared a draft program statement for the Chairman's forthcoming Budget j
hearings. Program Offices have reviewed and returned with their corrnents. A redraft was forwarded to OCM.
Budoet Briefing Information A highly sumarized version of the Green Book and possible questions and answers that could be asked by Congressional Budget Comittee members at the forthcoming hearings have been provided to the Chaiman.
Enclosure J e
N OFFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA ITEM OF INTEREST WEEK ENDING FEBRUARY 12, 1982 Case Study on Service Water System Flow Blockaces by Bivalve Moilusks at Arxansas Nuclear One ano Brunswick Following completion of the peer review process, AE0D recently issued a final report on several events involving service water blockages to safety-related equipment due to the presence of marine organisms. The report also notes that silt and corrosion products have caused flow blockages.
Accumulation of fouling organisms, silt or corrosion deposits each represent a potential mechanism for common cause flow blockage of the redundant trains in the service water system. The principal concern is that, with each of these mechanisms, degradation of service water system performance generally occurs slowly and may go unnoticed until systems required to function follow-ing an incident became inoperable due to a lack of cooling water.
The recomrendations in the report emphasize the need to expand the surveillance requirements in the plant technical specifications to assure that the cooling j
water flow supplied to each safety-related equipment cooler, room cooler, or i
heat exchanger is periodically verified to assure that the equipment will perform satisf actorily. Additional surveillance measures, such as verification of the overall heat transfer coefficient or visual inspection, may be necessary on multiple pass heat exchangers, since the measurerent of flow and differential pressure is not sufficient to guarantee the design performance of these heat exchangers if internal bypass leakage exists between passes.
With the awareness of the potential for fouling and implerentation of effective control and surveillance strategies, plants can be safely operated even at sites where fouling organisms such as Asiatic clams abound in the supply or receiving waterbodies.
The report has been issued to NRR and IE for appropriate action.
It is under-stood that NRR will include these and other sources of service water system malfunctions in their generic study of the problem.
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i REGION V WEEK ENDING FEBRUARY 12, 1982 Southern Califo aia Edison Company - San Onofre-2 On 2/10/82, the Regional Administrator notified the Division of Licensing, NRR that, except as noted, construction and pre-operational testing of San Onofre-2 had been completed in substantial agreement with docketed l
commitments and regulatory requirements and that Region V had no further items which would preclude issuance of a 5% interim operating license. The exceptions involved completion of the inspection of fire' barriers, the adequacy of surveillance procedures, the readiness of the radiochemical laboratory and process and effluent monitors, and the readiness of the post-accident sampling procedures. License conditions addressing these matters were recommended.
j In related activities, Region V also submitted to NRR:
(1) a summary i
report of the results of the Emergency Planning Appraisal Inspection i
as required by the ASLB, and (2) (on 2/11/82) the Region V input to the NRC evaluation of the General Atomic Interim Report on the Independent Design Verification Study for San Onofre-2.
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ITEMS APPROVED BV THE COMMXSSXON - WEEK ENDING FEBRUARY A2, 1982 A.
STAFF REOUIREMENTS - DISCUSSION OF QUALITY ASSURANCE /0VALITY CONTROL, 10:05 A.M., FRIDAY, JANUARY 29, 1982, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE), Memo Secy to Dircks, 2/10/82 The Ccr:raission was briefed by the staff on the status of varicus approaches to stre.qthening gaality assurance in traclear pcwer plants. The staff e phasized that these were gesals aM that they would be prepared to present a 2:cre detailed plan after the Ctrrission's meeting with iMustry representatives en Febraary 4.
The Cerrission regaested that:
1.
the staff examine the gaality control p+am used by FAA:
(IE)
(Sn suspense: 3/31/82) 2.
staff ascer~a5 and i::plement speedy procedures for reinstatecent cf CVCC ecployees wir are fired for wporting deficiencies; (IE) (SICY Suspense: 2/26/82) j 3.
staff provide an exacple of types of leers sent to licensees regaesting a finding that the plant was designed aM constracted in accordance with the technical specificaticns; ard (IE)
(SC Suspense: 2/15/82) 4.
staff provide a more defir.itive plan for i::grevement of the CA wa=, including s:M#ic tasks, personnel and fiscal regaimnents ad associated tiretables.
(IE)
(sir.'Y Susper.se: 3/31/82) i The Chai= an suggested that the C:rrissioners prcuide their ccrrnents to staff cn the items discussed. The staff indicated it was studying the c:r.sclida*4~1 of CVCC staff resources aM sculd report to the Ctrrission by mid-Feb: cary.
B.
STAFF REOUIREMENTS - AFFIRMATION SESSION 82-4, 3:50 P.M.,THUPISDAY, FEBRUARY 4,
)
1952, COMMISSIONERS' CONFERENCE ROOM, DC OFFICE (OPEN TO PUBLIC ATTENDANCE) l Memo Secy to Remick, 2/11/82 l
Procosed Policy Statement on Safety Goals for Nuclear Power Plants l
The Cc=ission, by a vote of 4-1 (Co=issioner Gilinsky disapproving), approved for publication in the Federal Recister a proposed Policy Statement on Safety Goals for Nuclear Power Plants, as circulated on February 3, 1982.
l The statement contains the joint views of the Chairman and Cc=issioners Ahearne and Roberts, separate views of Commissioners Gilinsky and Bradford, and additional views of Commissioner Ahearne.
(OPE)
(Subsequently,'at a meeting with the ACRS on February 5, the Cc=ission agreed to hold issuance pending miner modifications of the statement.
The statement was signed by the Secretary on February 11, 1982).
i ENCLOSURE N I
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