ML20009B382
| ML20009B382 | |
| Person / Time | |
|---|---|
| Issue date: | 07/10/1981 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-810703, NUDOCS 8107150344 | |
| Download: ML20009B382 (36) | |
Text
~
a
?l?ND Of July 10,1981
\\f.
/Q/
For:
The Commissioners f/y
~
From:
T. A. Rehm, Assistant for Operations, Office of the EDO
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING JULY 3,1981 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
Executive Legal Director F
International Programs G
State Programs H
Management and Program Analysis I
Controller J*
Analysis and Evaluation of Operational Data K*
Small & Disadvantaged Business Utilization L*
Items Approved by the Commissi
/
. A. Rehm, sis or Operations Office of the Executive Director for Operations
- No input this n ek.
Contact:
T. A. Rehm, ED0 49-27781 8107150344 810710 PDR COMMS NRCC WEEKLYINFOREPT PDR
i
SUMMARY
OF WEEKLY INFORMATION REPORT WEEK ENDING JULY 3,1981 Brunswick Unit 2 Following a nitrogen inerting system failure, a Technical Specification change was authorized to allow the licensee to continue operation for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> while making repairs.
ANO-2 and Hatch Unit 1 Both plants returned to operation following refueling and maintenance outages.
TMI modifications were also made.
TMI -- Submerged Demineralizer System (SDS)
The first waste water transfer from the Reactor Coolant Bleed Tank "B" to the SDS feed tanks comenced on June 30.
Decomissioning of the United Nuclear Facility at Wood River Junction On June 23, NRC staff met with representatives of the State of Rhode Island to commence preliminary negotiations on the agreement between Rhode Island and NRC relating to the decomissioning of the United Nuclear Facility.
Radiological Contingency Plans Copies of the recently completed Standard Review Plan for the Review of Radiological Contingency Plans for Fuel. Cycle and Materials Facility were mailed to those licensees who received orders requiring them to prepare radiological contingency plans.
Dismantling of the Lynchburg Pool Reactor On June 26, NRC staff met with the License Administrator for the Babcock &
Wilcox Lynchburg Pesearch Center (CRC) to discuss plans for dismantling the reactor license an1 transferring the facility to LRC SNM-778 Materials License (DocketNo.70-824).
l
{
L 0FFICE OF ADMINISTRATION Week Ending July 3,1981 ADf1INISTRATION OF THE FREEDOM 0F INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Received 293 9
Granted 214 1
Denied 35 6
Pending 44 2
ACTIONS THIS WEEK Received (NRC employee)
Requests sanitized copies of the original and (81-246) rewritten 1980 performance appraisals for five listed individuals.
Roger L. Boyer Requests a copy of the Rogovin Report, Kemeny (81-247)
Commission Report, and the 1979 and 1980 NRC Annual Reports.
John R. Kenrick, Requests six categories of information regarding Eckert, Seamans, the glove box explosion on November 30,1966 at Cherin & Mellott the Leechburg, Pennsylvania facility of Nuclear (81-248) tbterials and Equipment Corporation (NUMEC).
F. Ronald'Laupheimer, Requests all records relating to all F0IA requests Pacific Gas and made to the NRC referring to the Diablo Canyon
- Electric Company Nuclear Power Plant, Units 1 and 2.
(81-249)
Joseph H. White, III Requests six categories of documents regarding the (81-250)
Limerick Nuclear Generating Station.
Patricia Hinsberg, Requests a copy of SECY-81-253, relating to Financial ikGraw-Hill Protection for Three Mile Island Units 1 and 2.
Publications Company (81-251)
CONTACT:
J. M. Felton 492-7211 i
ENCLOSURE A l
i
-3 2
Granted Walt Brennan, In response to a request for recorded incidents Nixon and Company of radiation exposure to employees of the Crane
-(81-226)
Company and the results of any investigation the NRC may have performed as a result of these i
incidents, informed the requester the NRC does not have jurisdiction over X-ray machines.
X-ray machines are under the jurisdiction of the individual states.
(NRCemployee)
In response to a request for copies of her (81-232)
Personnel Performance Appraisal prepared by two named individuals, made available these records.
Kathleen M. Rowe, In response to a request for a list of all Gray & Rogers, Inc.
compan# as that are licensed in the US to package (81-235) or dispose of radioactive wastes as a service to hospitals, laboratories, and universities, made available this information.
Anne'Rapkin, In response to a request for a copy of "The Assistant Attorney Consequences From Liquid Pathways After a Reactor General, State of Meltdown Accident," by S.J. Niemczyk, of Sandia Illinois Laboratories, made available a copy of this (81-237) document.
Delissa A. Ridgway In response to a request for a copy of SECY Staff Shaw, Pittman, Requirements Memorandum S81-168 which reports the Potts & Trowbridge final action on SECY-81-168, " Proposed Rulemaking (81-239) to Reduce or Eliminate Requirements with Respect to Financial Qualifications for Power Reactors,"
made available a copy of this document.
Denied None ENCLOSURE a l
t DIVISION OF RULES.AND RECORDS
~
OFFICE OF ADMINISTRATION The Executive Director for Operations-has issued minor amendments to the NRC Notice of Systems of Records, NRC-18.
The amendments also revoke NRC-35. The amendments clarify and update the information contained in the NRC Systems of Records.
In the course of investigations, inspections, and audits, the Office of Inspector and Auditor frequently incorporates data from other systems which are exempt under (k)(6) of the Privacy Act.
This creates the need to add the (k)(6) exemption to the list available for NRC-18. -In System of Records NRC-35, the data collected for the IE Household Move Survey was used for a one-time compilation. All records were subsequently destroyed. The proposed minor amendments were published in the Federal Register on April 27,1981 (46 FR 23576) for a '30-day comment period. No comments were received.
[
e ENCLOSURE A
DIVISION OF SECURITY Week Ending July 2,1981 Classified S'afeguards Program A representative of the Facilities and Systems Security Branch conducted initial on-site security _ surveys of Babcock & Wilcox's Naval Nuclear Fuel Division and Lynchburg Research Center, Lynchburg, VA, in connection with 10.CFR Parts 25 and 95, " Access to and Protection of National Security Infor-
~
mation hnd Restricted Data."
f J
j ENCLOSURE A
0FFICE OF NUCLEAR REACTOR REGULATION WEEK ENDING JULY 03, 1981 BRUNSWICK STEAM L ECTRIC PLANT UNIT 2 On June 29, 1981, a Technical Specification change was authorized to extend
. by.72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> the time during which Brunswick 2 is permitted to operate after startup before bringing containment oxygen concentration within limits.
This emergency change was needed because an apparent vaporizer failure resulted in the introduction of liquid nitrogen into a pipeline outside containment designed only for gaseous nitrogen, thereby causing pipe rupi.da.
The licensee estimates that repairs will require seventy-two hours.
This is the second nitrogen inerting system failure at Brunswick within the last 30 days.
The licensee is reviewing the systems involved for possible design improvements.
AND-2 AND-2 co=enced its second cycle of operation cn June 30, 1981 after a 95 day outage.
Actions included in this outage were-(1) Fuel loading for a 12 month power cycle (2) Modification of reactor protection system (CPCS) computer software (3) Turbine maintenance (4) Steam generator inspection (5) Contain-ment leak rate testing (6) Service water system maintenance (7) Control room meter changeouts and (B) Other scheduled inservice inspection, surveillance and maintenance.
Other plant modifications (mods) based on TMI requirements included (1) TMI mods (2) Fire protection mods (3) Installation of a second main.
feestater isolation valve and (4) Installation of Overpressure Fcotection hardware..
Initial operation of the system is restricted to 70 percent of full power pending completion of the staffs review of the thermal margins maintained by the new CPCS software.
Operation of the plant will be limited to 80%
l cf full power pending replacement of one of the two main feedwater pump turbines.
The next refueling outage is currently scheduled for sumer of 1982.
l f
ENCLOSURE B
=,..
MEETING NOTIFICATION There will be an NRR meeting with INPO on July 2,1981 from 9:15 a.m. to 12:30 p.m. to have a technical exchange of Human Factors Programs. The contact i.s R. E. Ireland, NRR.
HATCH NUCLEAR PLANT, UNIT NO. 1 Hatch 1 started its Cycle 5 power operation on June 21.,1981 after a -113 day refueling outage.-
The work accomplished durin nominal 12-month cycle, (2)g the outage consisted of:(1) refueling for a Type B and C portions of Appendix J leak test program, (3) scheduled portions of the Inservice Ins scheduled surveillance testing and maintenance and (pection Program, (4)5) plac under river water intake structure.
NRC requirements were instituted as follows:
(1) modifications to the torus, (2) pipe support modifications per IE Bulletin 79-14, (3) implementation ~
of scheduled TMI mods per NUREG-0737, (4) equipment qualification mods per IE Bulletin 79-01B, (5) added audible alarms per IE Bulletin 79-18, inspected core spray spargers per IE Bulletin 80-19.
l l
l l
ENCLOSURE B
c, ilRC TMI PROGRAM OFFICE WEEKLY STATUS REPORT l[
wi Week of June 28 - July 5,1981 ll?
- , I Plant Status Core Cooling Mode:
Heat transfer from the reactor coolant system (RCS)
,y-
"y loops to Reactor Building ambient.
Available Core Cooling Modes:
Decay heat-remos.e4.sysress. - Len9-tare--
f; cooling "8" (once through steam generator-B) j]
- [.
RCS Pressure Control :4 ode:. Standby Pressure Control (SPC) System.
r.-
Backup Pressure Control Modes: Mini Decay Heat Removal (MDHR) System.
i Decay Heat Removal (DHR) System.
T.x Major Parameters (as of 0400, July 2,1931) (approximate values)
j Average Incore Thermocouples: il9'F yp Maximum Incore Thermocouple:
145*F
.p; RCS Loop Temperatures:
i A
B
.j; Hot Leg 118 F 121"F 7g Cold Leg (1) 71 F 73*F T
(2) 72*F 73*F g
RCS Pressure:
96 psig h
Reactor Building:
Temperature: 77?F n
.N:
Water level: Elevation 290.8 ft. (8.4 ft. from floor},
via penetration 401 manometer
' i.t.
Pressure:
-0.4 psig M
Concentration:
4.9 x 10-6 uCi/ml Kr-85 (Sample taken F
7/ l/81 d
.Q Effluent and Environmental (Radiological) Information to ic 1
Liquid effluents from the TMI site released to the Susquehanna River T
after processing, ware made within the regulatory limits and in g
accordance with NRC requirements and City of Lancaster Agreement Y3 dated February 27, 1980.
t
. -L During the period June 28, 1981, through July 5,1981, the effluents W
contained no detectable radioactivity at the discharge point and 9;
individual effluent sources which originated within Unit 2 contained W
no detectable radioactivity.
Jf
.g 76
'5,
.q fh
.R k';f.f Nb
.s I
ENCLOSURE B I
.9'
_ ~,,.s 3.:
2.
Environmental Protection Agency _ (EPA) Environmental Data _.
Results W
't from fPA monitoring of the environment arouna 'the iMI site were as
~
follows:
n'
[N 3
The EPA measured Kr-85 concentrations (pCi/m ) at several environmental monitoring stations and reported the following
(
results:
4.i Location June 19 - June 26, 1981
~ S 4,
(pci/m3)
.,n
- /'h Goldsboro 20 Observation Center 20 f
J.
Middletown Yorkhaven 20 l{!
- Results not available due to procedural difficulty.
/j)
.t All of the above levels of Kr-85 are considered to be back-
'i
,(!.
ground levels.
t
.W No radiation above normally occurring background levels..was detected in any of the samples collected from the EPA's air and ganma rate networks during the period from June 25, 1981, Y%
through July 2, 1981.
Wi w
3.
NRC Environmental Data.
Results from NRC monitoring of the environ-h ment arouiid the Dil site were as follows:
i
~
g The following are the NRC air sample analytical results for W
the onsite continuous air sampler:
Q m
I-1 31' Cs-137 p
Sample _
Peri _od juCi/cc) JuCi/cc)
.I HP-274 June 24,1981 - July 2,1981
<8.2 E-14 <8.2 E-14
,'h*
S; 3.!
4.
- - -Licensee Radioactive Material a_nd Radwaste Shipments On !!onday, June 29,1981, a 40 ml Unit 2 reactor coolant Yh sample was sent to Babcock and Wilcox (B&W), Lynchburg,; Virginia.
74 J(0 On Wednesday, July 1,1981, one cask containing 17 drums of Unit 2 LSA compacted and noncompacted waste was shipped to
'if U.S. Ecology, Richland. Washington.
llj dj On Thursday, July 2.1981, two liittman steel liners containing N
'js Unit 1 solidified evaporator bottoms were shipped to U.S. Ecology, Richland, Washington.
- .y q
Da.,
$Ef IhN TE k.+.
g.---
ENCLOSURE B g
,- m
- 4 y
Major Activities 3,
p' ':
1.
Submerged Demineralizer System (SDS1 The first waste water transfer from the Reactor Coolant Bleed Tank (RCBT) "B" to the SDS g,6 feed tanks commenced on June 30, 1981.
The RCBT "B", which contains q
waste water generated durina the decontamination of the Unit 2 Auxiliary Building, is schehuled to be processed in two 50,000 gallon 9
ef batches. Transfer of one batch was completu July 5,1931.
RCBT "B" water was transferred through two particulate filters (pre and Q
final) into the SDS feed tanks.
After minor startup problems, the i
evolution proceeded smoothly.
Processing through ion exchange y
vessels is tentatively scheduled to begin during the week of July 6, 1981.
ll$
im The TMI Program Office has currently approved 21 of the 37 required
.{
procedures to operate.the SDS.
These 21 procedures were required 3
to be approved prior to DCBT "B" transfer to the SDS feed tanks.
rig The remaining procedures need NRC approval p. f or to SDS processing.
. ~,g Functional testing of the remaining parts of the SDS have been M
completed with the exception of the zeolite vessel trains.
Operator training for processing feed tank water through the SDS is
@U
.T}
continuing in conjunction with system functional testing and-f zeolite vessel loadings.
.tM 2.
EPICOR-II Liner _ Disposal.
On June 30, 1981, the last 2 (of 22)
.Tg second and third stage EPICOR-II liners reached the burial site in M
Hanford, Washington.
These liners were generated during the
. 2) processing of contaminated water through the EPICOR-II system.
The
,h EPICOR-II system was used to process Auxiliary Building water M
.A (approximately 500,000 gallons) from the March 28, 1979 accident.
' i Forty-nine first stage prefilter (PF) EPICOR-II liners are still
?k stored on site.
The best method of disposal for these higher
- ..,j activity liners is being evaluated at the present time.
One of the l
higher activity liners (PF-15) was shipped to Battelle Northwest Ts Laboratories for analysis on May 19, 1981.
".h 3.
Reacto_r Building' Entry.
Four men inspected and surveyed the Unit 2 c
Reactor Building (RB) polar crane during a RB entry on July 1,1981.
- )
Six of the 14 polar crane motors were.meggered during the two hour.
TE; inspection.
The resistance between the motor phases and ground, as
M
@M measured at a comon junction box, ranged between 0.2 and 0.5.&gohms.
The licensee is evaluating the significance of these measurements, although the low resistance suggests that the motors may be damaged.
,y Insulation on some crane power cables was damaged to the extent that bare conducting wires were visible.
The padding on the seat
.$y of the crane operator's chair was burned ar.d charring in the crane d
cab appeared to indicate the presence of flames during -the March 28, 1979 F
accif.ent.
Crane mechanical components appeared undamaged although patches of rus'. werc evident.
The licensee is evaluating what 3
repairs will be neces ary before the crane can be used to remove the reactor vessel head.
2
.'1 t
%v 7-r ENCLOSURE B
- l
~
Aw g
-4~
Itk Upon exiting the RB, the entry team underwent rcutine " frisking" y) for radioactive contamination.
Contanination was found on the skin V
of all four individuals.
The primary areas of contamination included the buttocks, elbws, and knees.
Personnel decontamination
- i.
procedures were initiated and after several hours, three of the W
fcur individuals were decontaminated on July 1,1981.. The buttock jj of the fourth individual was not completely decontaminated until si the following day.
./c?
..th The skin contamination apparerttly resulted from climbing on con-4; taminated crane surfaces in perspiration soaked protective clothing.
Following several instances 'of personnel exhaustion during RB entries, the licensee relaxed the criteria for use of plastic
'N protective clothing in the R8 to reduce fatigue and the crane h
inspection team was wearing only two sets of protective clothing.
The outer layer of protective clothing was advertised by the AO manufacturer as water impermeable.
The same type of protectiv iiij clothing had been worn during the initial climb on the crane wiun 9,2; no instances of skin contamination.
The second crane climb was ti:
physically more demanding and all team members exited from the RB 5,1I exhausted with the inner layer of protective clothing completely
..$p q
soaked.
The licensee is evaluating the available information to j
determine what comt'ination of protective clothing is required for
- g future entries.
g,.)
'id
ff The next RB entry is scheduled for July 23, 1981.
m
- '!h tYs ilf
~
a.u 14
.Mi
.3 m
lW
.. hk Ni w
.n N;
'.ll
- g h*
to; fer 9.' $
.M k
.!h
+:;
.yN
\\
0l, ENCLOSURE B
]'
~~}
y
$S 06' Meeting Held
- v.
dn Wednesday, July 1,1981, Lake Barrett met with area mothers to
.gr discuss various subjects related to TM1.
Topf cs included gas generation 4:
in stored EPICOR-II prefilters, how the NRC audits licensee radiological
/ef.
analyses by independent measurements, SDS and cleanup progress.
jf h
Future Meeting 65 i
'On Thursday, July 9,1981, the Advisory Panel for the Decontamination of Three Mile Island, Unit 2 will be meeting from 7:00 p.m. to 10:00 p.m.
,in the Holiday Inn, 23 South Second Street in Harrisburg, to discuss the This meeting will be open
. 4.r current status of cleanup activities at TMI.
4 for public observation.
.t i
'N 1
. {.):
a 3;.
.j.
if x.m
.ep
- 3. :,
,We q;:
.y.,
- [9l
.lh-9
.?
?n A.
lg.,
Iffi M.
y,:
- chi
$u;
- a
','s.
4:
.4
.;d.W
- e c.
- W
' U.'h..
4t:
.a:
. n..
.d,tj
- 2%..
.ar EhCLOSURE B A;5
~~
k
0FFICE OF NUCLEAR MATERIAL, SAFETY AND SAFEGUARDS Items of Interest Week Ending July 3,1981 Radiological Contingency Plans Copies of the recently conpleted Standard Review Plan for the Review of Radiological Contingency Plans for Fuel Cycle and Materials Facilities were mailed to those licensees who received orders requiring them to prepare a radiological contingency plan.
Dismantling of the Lynchburg Pool Reactor On June 26, 1981, NRC staff met with A. F. Olsen, License Administrator for the Babcock & Wilcox (B&W) Lynchburg Research Center (LRC) to discuss plans for dismantling Lynchburg Pool Reactor, terminating the associated reactor license and transferring the facility to the LRC SNM-778 Materials License (Docket No.70-824).
Criteria were given Olsen for developing the LRC dismantling and decontamination plan for NRC review prior to performing the proposed dismantling operation. A similar procedura was followed in 1972 for the dismantling of the LRC BAWR (B&W Test Reactor). The proposed schedule for the dismantling process is as follows:
(1) ship fuel by 12/81, (2) begin dismantling in 1/82, and (3) complete dismantling by 7/82 followed by termination of the reactor license and NRC authorization to transfer the facility to the SNM license.
NFS' Environmental Monitoring Program f
l A meeting was held with a representative of NFS, Erwin to review recent l
results of their environmental monitoring program and to discuss the need for additional upgrading of the ventilation system.
Environment air particulate samples collected at the nearest residence in the first week of Jun 1981, indicated an air concentration of radioactivity of 1 x 10-T5 uc/ml.
If this concentration level continues, the Erwin plant would meet the 25 mrem / year limit of License Condition 66 regardless of solubility of the material. Actual lung fluid soiubility tests of collected particulates varied widely but averaged 50% soluble meeting the 1 x 10")gFS continues to have difficulty in consistently and 50% insoluble.
uc/ml stack limit imposed by license conditions.
ENCLOSURE C
a Items of Interest 2
Because the environmental impact of stack releases appears to be low, NRS questioned the need for continuing the stack limit and requiring additional ventilation system improvements. The staff position on continuing the stack limit is that the environmental monitoring results at the nearest residences are too limited to conclusively demonstrate that the 25 mrem / year limitation will be met on a long term basis and that until compliance with the 25 mrem / year requirement is well demonstrated, no action to remove or change the stack limitation will be taken.
Decomissioning of the United Nu:: lear Facility at Wood River Junction On June 23, 1981, staff members met with representatives of the State of Rhode Island to comence preliminary negotiations on the agreement between the State of Rhode Island and the Comission relating to the decomissioning of the United Nuclear Facility at Wood River Junction, Rhode Island. The state was given copies of other State /NRC agree-ments ta provide them with ideas for an acceptable format.
The items listed Governor Garably's letter to Chairman Hendrie were discussed ir detail and it was agreed that additional information would be gathered by both parties before meeting again to start drafting the format agreement.
Meeting with the Rhode Island Coalition for Consumer Justice On June 4,1981, an FC representative met with the Rhode Island Coalition j
for Consumer Justice (CCJ) in Wakefield, Rhode Island to discuss the decomissioning of the UNC facility and some of the concerns the Coalition has regarding the site. Their main concern centered around the possiblity that United Nuclear many abandon the site leaving contaminated waste and a contaminated aquifer. The meeting was fruitful in putting to rest some of their concerns. CCJ requested that a similar meeting be held on August 5,1981. They were informed that the staff would meet with them periodically, but we would itke to schedule the meetings around dates when we would also be in the area on other business. CCJ agreed that a firm date for the next meeting would be selected at a later date.
l Regional Licensing Program On July 1,1981, the Material Licensing Branch, Division of Fuel Cycle and Material Safety instituted a regional licensing program in which selected parts of its materials itcensing program is being conducted in i
Region I.
Non-Agreement States in Region I are involved in the regional i
licensing program. Federal facilities within these states and the i
District of Columbia are excluded from the program.
j i
ENCLOSURE C
Items of Interest 3
. Society of Nuclear Medicine Award On June 16, 1981, the Society of Nuclear Medicine presented its Distinguished Service Award to Mr. Richard E. Cunningham, Director of Fuel Cycle and Material Safety, during the plenary session of its annual meeting. The award citation reads:
"For his tireless efforts in the development of a safe and rational radiation protection philospfly for the American public and for the practice of nuclear medicine."
Visit to MIT Research Reactor, Members of the Division of Safeguards visited the MIT research reactor on June 25, 1981, in conjunction with a draft generic issue paper on the consequences of sabotage at Category II/III facilities. The staff members learned that the MIT reactor had been redesigned several years ago to preclude various consequences of any sabotage attempt.
Vital Area Designation & Protection Requirements Safeguards is now circulating a staff paper containing proposed revisions to 10 CFR 73.55 concerning the designation and protection of vital areas at nuclear power plants.
The proposed vital designation technique holds the potential for reducing the number of such areas ultimately requiring safeguards protection. The paper should reach the Consnission by mid-sumer.
ENCLOSURE C
Planned Meetings - Division of Waste Management 1.
Subject:
Review processes and programs and rehabilitet*en of tailings dams.
Date:
July 3, 1981 Location:
Willste Building Attendees: Mr. W. J. Wright, Australian Embassy; R. A. Scarano, WMUR 2.
Subject:
Prelicensing Date:
July 7,1981 Location:
Willste Building.
Attendees: Uranerz of Wyoming; H. Pettingill, WMUR 3.
Subject:
40CFRi90 Date:
July 7, 1981 Location:
Willste Building Attendees: Bear Creek; R. A. Scarano, WMUR 4.
Subject:
LLW Management Program Date:
July 9, 1981 Location:
DOE; E. Tourigny, WMPI
)
l l-ENCLOSURE C
Planned Meetings Division of Safeguards 1.
Subject:
Incorporate US/IAEA Agreement Facility Attachment data into the NMMSS System Date:
July 7-8,1981 Location:
Oak Ridge, Tennessee Attendees:
Gene Sparks, June Robertson, SGMD/NMSS Representatives of DOE and Union Carbide 2.
Subject:
Meeting at New Brunswick Laboratory to participate in the Safeguards Analytical Laboratory Evaluation (SALE) program Date:
July 8-9, 1981 Location:
Argonne, Illinois Attendees:
D. Joy, SGML B. Moran 3.
Subject:
Verification of Inventory of Canadian Origin Material Date:
July 9-10,1981 Location:
Oak Ridge, Tennessee Attendees:
Gene Sparks, June Robertson, SGMD Representatives of DOE and Canadian Government
~4.
Subject:
Meeting with GE-Morris to review Safeguards research relevant to spent fuel sto; age.
Date:
July 10,1981 Location:
Morris, Illinois Attendees:
D. Joy, SGML G. Engels 5.
Subject:
INMM.14 Subcomittee on International Safeguards
'tandards and INMM Annual Meeting Date:
July 12-15, 1981 Location:
San Francisco, California Attendees:
Kenneth Sanders, SGMD Representatives from IAEA, GE, Exxon, TVA, AGNS, DOE, PNL, BNL & others 6.
Subjet.t:
To attend the Institute of Nuclear Materials Management (INMM) meeting Date:
July 13-15, 1981 Location:
San Francisco, California Attendees:
H. Bartz, SGML 7.
Subject:
INMM Annual Meeting Date:
July 13-15,1981 Location:
San Francisco, California Attendees:
T. S. Sherr, M. Messinger, SGMD 8.
Subject:
Verification of Inventory of Australian Origin Material l
Date:
July 13-14,1981 l
Location:
State Department, Washington, D. C.
l Attendees:
lene Sparks, June Robertson, SGMD l
embers of DOE, State, and Australian Government L
ENCLOSURE C
2-Division of Safeguards - Planned Meetings (continued) 9.
Subject:
To attend an American National Standards Institute (ANSI)
Sub-committee Meeting Date:
July 16, 1981 Location:
San Francisco, California Attendees:
H. Bartz, SGML 10.
Subject:
Meeting with GE-Vallecitos to review decommissioning activities Date:
July 17,1981 Location:
Vallecitos, California Attendees:
D. Moschner, GE H. Bartz, SGML 11.
Subiect:
" Design Features for Facilitating IAEA Safeguards" Contract Review Meeting Date:
July 16-17, 1981 Location:
San Francisco, California Attendees:
Kenneth Sanders, SGMD Neil Harms, PNL; John Glancey, SAI; Carl Bennett, HARC, John Jaech Exxon Absences of Director or Deputy Director Robert F. Burnett - July 6-10, 1981 - Acting:
Donald R. Chape11 Donald R. Chape11 - July 15,1981 I
ENCLOSURE C L
Meetings - Division of Fuel Cycle and Material Safety 1.
Subject:
Discuss the New, Completely Proposed, Dry Conversion Line at the South Carolina facility (Westinghouse).
Date/ Time:
July 7 - 9:00 Location:
Rcom 470 - Willste Building Attendees:
E. Rietler, C. Sanders, (Westinghouse - South Carolina);
W. T. Crow, R. L. Stevenson, G. Bidinger, (NMSS)gh);
R. Williams, J. Nardia, (Westinghouse - Pittsbur ABSENCES OF DIRECTOR OR DEPUTY DIRECTOR Thomas F. Carter, Jr. - July 13-17 (Leave)(tentative) 9 I
s P
l l
i ENCLOSURE C
OFFICE OF INSPECTION AND ENFORCEMENT Items of Interest Week Ending July 2,1981 1.
The following Notifications of Significant Enforcement Acticn were dispatched during the past week:
a.
EN-79-16A Consumers Power Company (Palisades Nuclear Power Facility) - An Order Imposing Civil Penalties in the amount of $450,000 was previously issued to subject licensee on Decemoer 20,1979 (EN-79-16). This action was based on three alleged items of noncompliance which involved violation of containment integrity.over a period of about 17 months. The licensee requested a hearing and an agreement was reached whereby Consumers Power The Company agreed to pay civil penalties in the amount of $225,000.
settlement notes dispute over the length of time containment integrity was not maintained but notes that containment integrity was violated in excess of one day when the plant was in other than cold shutdown.
b.
EN-81-22 Pharmaco Nuclear, Inc., Cleveland, OH - A Notice of Violation and Proposed Imposition of a Civil Penalty in the amount of $2,800 was issued on July 1,1981 to subject licensee.
This action was based on an alleged violatim involving loss of attache cases containing radiopharmaceuticals during transport and delivery to'several local hospitals. The licensee took imediate steps to correct the problem, and immediately notified the NRC.
It was therefore determined that a 30 percent reduction in the civil penalty from $4,000 to $2,800 was appropriate.
2.
Preliminary Notifications relating to the following actions were dispatched during the week:
a.
PN0-I-81-71 Indian ' Point Unit 2 - Overflow of Resin Cask b.
PN0-I-81-72 UNC Recovery Systems, Wood River Junction, R.I. - Breach of Plywood LSA Radioactive Waste Shipping Box c.
PN0-II-81-47 Crystal River Unit No. 3 - Unplanned Outage d.
PNO-III-81-59 Palisades Nuclear Power Plant - Diesel Generator and Shutdown Sequencer Inoperability e.
PNO-III-81-61 Davis Besse - Extended Shutdown Due to Immovable Control Rod f.
PNO-V-81-35 San Onofre Nuclear Generating Station, Unit No.1 - SONGS 1 Allegations During SONGS 2/3 ASLB Hearing PN0-V-81-36 U.S. Ecology, Inc., Beatty, Nevada Burial Site - Banning of g.
Public Service Electric and Gas Company, Newark, New Jersey (NRC Licensee) for Radioactive Waste Shipment ENCLOSURE D
2-h.
PN0-V-81-37 U.S. Ecology, Inc., Beatty, Nevada Burial Site - Banning of United Nuclear Corporation, Wood River Junction, Rhode Island (NRC Licensee) for Radioactive Waste Shipment i.
PN0-TMI-81-13 Three Mile Island, Unit 2 - Epicor-II Liner Shipment j.
PNS-V-81-06 San Onofre Nuclear Generating Station - Bomb Threat 4
i e
ENCLOSURE D
-- - - l
0FFICE OF NUCLEAR REGULATORY RESEARCH IliPORTANT EVENTS FOR THE HEEK ENDING JULY 3,1981 A.
Exoerimental Programs Branch 1.
Semiscale The first test of the natural convection series. S-NC-1, was successfully conducted on June 24,1981 (ahead of the working schedule date of July 1,1981).
Five steady state data sets were obtained for various combinations of power, primary pressure and secondary pressure. Test S-NC-2, with single phase, two-phase and reflux conditions, is scheduled for July 15, 1981.
The initial report cov'ering testing of the Westinghouse level detector is to be mailed on July 29, 1981.
This report has a limited distribution. Broad reporting will be provided by ORNL following their analysis of the test data.
The Semiscale FY 1981 test program is being replanned following the cut from the requested $8.4H to $7.1M. The fonner value would not have maintained the FY 1980 level of effort.
2.
BWR FIST Program Work on the BWR FIST is progressing. The Division of Contracts issued approval of a list of anticipated subcontracts with dollar limits.
This prior approval will allow GE to issue subcontracts within dollar limits with PMG concurrence.
The PMG approved subcontracts for engineering necessary to obtain local building permits and for computer charges at INEL.
INEL is having difficulty finding staff for the GE site representative position. However, INEL staff will spend time at GE during the next few months while key scaling and design e ~>rts are in progress.
3.
LOFT Preparations are continuing for a containment integrity test on July 9,1981.
Detailed test requirements have been discussed with NRR Containment Systems Branch. All work is progressing smoothly for an end of July L6-7/L9-2 simulation of the ANO turbine trip and St. Lucie cooldown transients.
As an aid in establishing the contingency tests to be run, RES and EG&G/D0E have worked out criteria for the test.needs. These will be discussed with the ACRS-ECCS subcommittee next week.
The presentations which were prepared for the ACRS-ECCS subcommittee meeting,which was canceled last week,have been reviewed and modified for future presentation. New presentations, on a new format, will be given when the subcomittee meets on the new schedule date, July 7,1981.
ENCLOSURE E t_
. The schedule for the WRSR Infonnation Meeting has been established.
Integral systems. tests, including LOFT, Semiscale and the foreign systems tests, will be handled on the.first day of the meeting.
4.
FLECHT SEASET Testing of the last 21 rod blocked bundle is in progress. Westinghouse successfully conducted two steam cooling tests this week. The monthly projection estimates that the program is on schedule, both in cost and time.
B. Analytical Models Branch 1.
Three meetings have been scheduled to accompany the expected release of the TRAC-PF1 code on July 30, 1981.
a.
A presentation of PFl capabilities to NRR on August 4, 1981 in Bethesda, b.
A review of the code by the Advanced Code Review Group on September 21, and 22, 1981 in Silver Spring.
c.
A workshop for code users on September 29, - October 1, 1981 at LANL.
2.
The AMB staff is preparing for the July 7, 1981 meeting with the ACRS (F Nsset subcommittee) on Code Development and Assessment.
3.
CCTF-CORE I tests have been completed and the data from parametric-variation tests is currently being analyzed in both Japan and the U.S.
The data from most parametric tests are quite similar to the base case test, but the differences are worth noting.
In one parametric test, the LPCI flow rate was doubled that from the base case; all other test variables were held the same.
The overall core response for this test was almost identical to the base case because almost all of the additional LPCI flow was bypassed out the break, once the downcomer filled up to its maximum level.
Two tests varying only the system pressure were run.
In one, the pressure was higher (45 psia) than the base case (30 psia), and in theothertestthepressurewaslower(23 psia). As the pressure.
increased, steam binding effects were reduced, core cooling improved, and the core quenched earlier (about 100 seconds earlier in the high pressure run than the base case).
ENCLOSURE E
. C. Severe Accident Assessment Branch Severe accident Sequence Analysis (SASA)
Guy Vissing (NRR, Licensing) has arranged a :aeeting at Little Rock, Arkansas,'on July 30 with Arkansas Porter and Light ( AP&L) Co. to propose participation of AP&L in the Severe Accident Sequence Analysis (SASA) program. The meeting is.a follow-up to discussions b che SASA Program Review Meeting (May 29-30, 1981) and to a letter issued to AP&L management by D. Eisenhut (NRR-LIC) proposing that the Arkansas Nuclear One (ANO-1),
Unit 1 ( a BW nuclear steam supply system) Se used (in a manner similar to the W Zion and the GE Brown's Ferry Plants) as a base for SASA calcula-tions. -The principal contribution of AP&L would be the supplying of as-built dimensions and plant operating data on ANO-1, Unit 1 to be used for severe occident analysis by best estimate computer models and codes as part o+ the FY-1982 SASA effort. Bob Curtis, Guy Vissing and the four SASA ccntractor managers are probable attendees to the July 30 meeting.
A SASA Steering Group Meeting (Curtis plus the four SASA contractor managers) is being planned for July 29, also in Little Rock.
D.
Division of Engineering Technology Dr. Spencer Bush and Dr. Dave Okrent, members of the Review Group to the Nuclear Safety Oversight Comittee, are assigned to write a cortion of a report related to research programs on structural engineering, mechanical engineering, materials engineering, and fuel behavior.
The NSOC report is scheduled to be completed in August 1981. A meeting was held in Denver on June 17 to discuss the structural, mechanical and materials engineering research. Present in the meeting were Spencer Bush, L. Shao (Division of Engineering Technology) and Ted Marston (EPRI). The subjects that were covered in this meeting were:
l.
Comparison of NRC and EPRI programs; 2.
The issues that the research programs will help resolve; 3.
Areas where data and programs are considered inadequate; 4.
Any areas that are overly emphasized; and 5.
The mechanisms that can be undertaken in order for the licensing staff and the utilities to fully utilize research results.
l, 5
4 ENCLOSURE E
N 4
~
. E.
Program and Administrative Services Branch Signing of FD-4 Safety Research Agreement with KfK,'F. ~R. Germany On 1 July 1981, the Executive Director For Operations signed, on behalf of the NRC, a cooperative safety research agreement with the Kernforschungszentrum Karlsruhe (KfK) providing for a KfK-funded FD-4 series of fuel rod disruption tests to be performe'd at the Sandia National Laboratory.
Under the terms of the agreement, the KfK will make a finanical contribution of $250,000 to cover the full incremental costs of the test series. These tests will supplement a similar FD-2 test series being sponsored by NRC at Sandia to investigate the timing and mode of failure of irradiated'LMFBR? fuel rods under loss-of-flow (LOF) accident conditions.
The information to be obtained has significant implications with regard to understanding the reactivity changes in the core that may develop during a LOF accident, and thereby the overall severity of the accident consequences.
The signed agreement has been transmitted to FRG for signing hy an official of the KfK.
Publications to be Issued in the Near Future
Title:
Standard Format and Content Guide for the Nuclear Reactor Access Authorization Rule (Draft Regulatory Guide)
Expected Issuance Date: August 1981
==
Description:==
This guide provides the standard format and content for access authorization plans to be submitted pursuant to the proposed section 73.56.
Contact:
H. Tovmassian 443-5976
Title:
A Review of the Reliability of Auxiliary Feedwater Systems in Nuclear Power Plants Designed by B&W (NUREG)
Expected Issuance Date: September 1981
==
Description:==
This report presents the results of the !RC staff review of the reliability analysis performed by B&W of the auxiliary feedwater systens in operating pressurized water reactors designed by B&W.
Contact:
K. G. Murohy 443-5921 ENCLOSURE E
e 0FFICE OF THE EXECUTIVE LEGAL DIRECTOR ITEMS OF INTEREST WEEK ENDING JULY 3,1981 i
William B. McGuire Nuclear Station, Units 1 and 2 In an Order served on June 29, 1981, the Commission authorized the Director, NRR to issue a full power, full term operating license for Unit 1.
Virgil C. Summer Nuclear Station, Unit 1 In a Decision (CL1-81-14) served on June 29, 1981, the Commission denied the petition of the Central Electric Power Cooperative, Inc. for an affirmative determination with respect to significant changes as to antitrust matters.
The effect of the Decision is to preclude statutory antitrust review of the applicants in connection with their pending application for a license to operate Unit 1.
Farley Nuclear Plant, Units 1 and 2 On June 30, 1981, the Appeal Board issued a Decision (ALAB-646) in this antitrust proceeding.
The ASLB ruled that the licensing of Units 1 and 2 would create and maintain a situation inconsistent with the antitrust laws within the meanirig of the Atomic Energy Act unless certain remedial conditions were included in the licenses. The Appeal Board modified the ASLB decision and affirmed it as modified.
McGuire Nuclear Station', Units l 'and 2 On July 1,1981, the Appeal Board issued a Memorandum and Order (ALAB-647) in which it denied the intervenor's motion to stay the effectiveness of the ASLB's initial and supplemental initial decisions pending the disposition af exceptions, I
l ENCLOSURE F
ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING JULY 2,1981 Foreign Visits to NRC On Monday Messrs. Milella, Pino, and Pranzo of the Italian National Nuclear Energy Committee (CNEN) met with H. Graves, RES, H. Wong, IE, and M. Hartzmann, NRR, to discuss technical questions related to piping supports.
On Tuesday Mr. Peterson of the Australian Atomic Energy Commission met with R. Blond, RES, to discuss radiation transpcrt models and risk assessment.
l i
i i
i i
ENCLOSURE G l
s e OFFICE OF STATE PROGRAMS.
ITEMS OF INTEREST WEEK ENDING JULY 2,- 1981 On June 25 and 26, 1981 Bob Trojanowski, State Liaison Officer, Region II,. participated in.a low level radioactive, toxic, and hetardous waste cymposium and workshop at the University of Florida in Pensacola, Florida.
On June 29 and 30, 1981 Bob attended a regional State low level waste compact meeting in Asheville, North Carolina.
These compact meetings are being conducted in an effort to develop a draft low level waste compact for presentation to the respective governors at the Annual Southern Governors' Conference scheduled for September 1981.
The next scheduled low level waste compact meeting is set for August 3.and 4, 1981 in Atlanta, Georgia.
Final language was agreed to on a Protocol for the Conduct of 1
Joint Hearings with respect to the Skagit Nuclear Power Project.
Nicholas Lewis, Chairman, and other representatives of the Washington State Energy Facility Site Evaluation Council met on July 1, 1981 in Bethesda with B. Paul Cotter, Chairman and Dr. Rober t Lazo, Executive Vice Chairman,-ASLB, regarding the Protocol which would be promulgated under the general Memorandum of Agreement between Washington and the NRC dated September 6, 1978.
Staff members from OSP, ELD and NRR also participated in this. final drafting session.
9 4
t I
ENCLOSURE H L
O 0FFICE OF MANAGEMENT AND PROGRAM ANALYSIS Items of Interest WEEK ENDING JULY 3, 1981 NRC's Long Range ADP Plan Circulated first draft to Offices and requested coments by July 17. Expect to complete plan in August.
b 4
k 4
ENCLOSURE I
=_
ITEMS APPROVED BY THE COMMISSION - WEEK ENDING JULY 3,1981 A.
STAFF REQUIREMENTS - COMMISSION MEETING ON MCGUIRE, 2:10 P.M., WEDNESDAY, JUNE 24, 1981, COMMISSIONERS CONFERENCE ROOM, DC 0FFICE (OPEN TO PUBLIC ATTENDANCE). Memo for the Record fm SECY, dtd 6/26/81..
The Comission was briefed by J. Michael McGarry and William Porter (Duke Power Co.); Edward G. Ketchen and Joseph Scinto (NRC); and Jesse Riley (CESG), parties to the McGuire operating license proceeding.
The Commission had asked the parties to address the following questions:
1.
In view of the fact that substantial quantities of hydrogen were evolved during the TMI accident before containment pressure si nificantly 3
exceeded 3 psig, 'what is the basis for selecting the 3 psig containment pressure signal as the appropriate trigger for energizing the igniter system? Should the trigger instead be safety injection?
2.
In view of the fact that the effectiv.eness of.the hydrogen control system depends in part on operation of air return fans and the hydrogen skimmer fans in conjunction with the igniters, is it reasonable to switch on the igniters at a lower pressure than the trigger set point for the air return fans 'and the hydrogen skimer fans?
Is it feasible to switch on the air return fans and hydrogen l
.skimer fans at containment pressures less than 3 psig without the
~
possibility of negative containment pressure or other adverse factors?
t B.
SECY-81-367 - DIRECTOR'S DENIAL OF 2.206 RELIEF (IN THE MATTER OF GULF STATES
' UTILITIES).
Memo SECY to Bickwit, dtd 6/26/81.,
This is to advise you that the Comission (with all Comissioners approving) has decided there is no need for a review of this decision of the Director, Office of Inspection and Enforcement.
I C.
STAFF MARCH 4, 1981 PROPOSAL TO DELAY POST-CP CHANGES RULE INDEFINITELY. Memo SECY to Dircks, dtd 6/30/81.
This is to advise you that a majority of the Commission desires that the staff develop the post-CP rule by December 1, 1981.
Chairman liendrie concurred with the staff's March 4 recommendation to postpone further work on the proposed rule for a year.
l In connection with his approval, Commissioner Gilinsky had i
the following comments:
"The rule should specify when a j
change requires notice to the NRC, NRC approval, or a CP amendment and give examples for each category.
The rule should not attempt to categorize all conceivable changes in advance.
I would rather have a workable rule this year and develop its application on a case-by-case basis than have an encyclopedic listing of all possible changes five years from i
now."
i This completes SECY action on COMPB-81-2.
TELO31RR
=
. D.
RAISING OF ' ISSUES SUA SPONTE IN ADJUDICATORY PROCEEDINGS. Memo SECY to Rosenthal/ Cotter /Bickwit, dtd 6/30/81.
On' June 2, 1981, the Commission requested that henceforth:
(1)
Ehen a Licensing Board or an Appeal Board raises' an issue sua sponte in an Operating License proceeding, it shall issue a separate order making the requisite findings, briefly state its reasons for raising the issue;and it shall forward a copy of that order to the Office of the General Counsel and to the Co.enission and (2) when a Licensing Board or an Appeal Board has raised an issue sua sponte, the Office of the General Counsel shall, as part of its regular monitoring of adjudicatory proceedings, make a prompt report on the matter to the Commission.
j The Commission made clear that in so requesting, it was not altering in any way the provisions of the Commission's rules regarding the raising and consideration of issues sua sponte.
Accordingly the Boards shall continue to make the initial-determination of whether a Board question is an exercise of sua sponte authority or a question asked to ensure the l
completeness of the record on an admitted contention.
'Furthermore, the fact that an issue has been raised sua' sponte, and that the Commission will be advised of that action by the Office of the General Counsel through its
]
monitoring of adjudicatory proceedings, would not provide a basis for any party to fail to meet its obligation to respond i
expeditiously to the Board's questions.
This completes action on SECY-81-30'4B.
E.
SECY-81-231 - AMENDMENTS TO 10 CFR PART 19 TO ESTABLISH NRC STAFF AUTHORITY TO CALL MEETINGS WITH LICENSEES.
Memo SECY to Dircks, dtd 6/30/81.
4 This is to advise you that-the Commission has disapproved the subject paper.
Commissioner Ahearne, with Chairman Hendrie and Commissioner Bradford agreeing, recommended'.that the Commission follow the advice of the EDO (June 2, 1981 memorandum to Commissioner Ahearne) who suggested that-appropriate rule-changes in other parts of 10 CFR be made.
Commissioner Ahearne and Chairman Hendrie would do this as part of the five year j
regulatory review process.
1 ENCLOSURE M
. - ~ - -
, F.
SECY-81-333 - REEXAMINATION OF THE MEDICAL MISADMINISTRATION RULE. Memo SECY to Dircks, dtd 6/30/81.
This is to advise you that the Commission has disapproved your recommendation to solicit public comments on the reexamination of the medical misadministration rule.
The Commission has agreed that analysis and review of the
'first 12 months experience is appropriate and should be accomplished.
Upon completion of the review and evaluation of the data chairman Hendrie and Commissioner Ahearne would be prepared to consider a public comment period on re-examination of the rule.
The Commission agreed that discussions with JCAH and FDA, to determine if they would be appropriate government agencies to take over this activity, should be initiated.
Commissioner Bradford agreed with this as long as the talks do not infringe on analyzing the misadministration reports and taking proper enforcement action.
G.
SECY-80-518 - CONSIDERATION OF ACRS LETTERS IN ADJUDICATIONS: ROLE OF ACRS IN ESTABLISHING NRC SAFETY FRIORITIES. Memo SECY to Bickwit/Rathbun, dtd 6/30/81.
This is to advise you that the Ccmmission has been unable to agree on the proposed Policy Statement on the role of ACRS letters in adjudications.
~ Comissioner Ahearne would encourage the Boards to notify the Comission of any issues raised by the ACRS which they believe have not been adequately resolved--leaving it to the Commission to decide whether the issue should be pursued through the adjudicatoiy process or by some other means. Chairman Hendrie agrees with this approach.
The Comission has approved the obtaining of ACRS comments on draft unresolved safety issues reports. (NRR)
H.
STAFF REQUIREMENTS - GENERAL' ADMINISTRATIVE MEETING, 2:20 PM, MONDAY, JUNE 29, 1981, COMMISSIONERS CONFERENCE ROOM, DC 0FFiCE (OPEN TO PUBLIC ATTENDANCE).
Memo for the Record fm SECY, dtd 6/30/81.
1.
The'Comission, by a vote of 3-0<, approved a draft staff requirements memorandum regarding the ASLBP % del Hearing Schedule.
l (Subsequently, the Secretary signed the SRM.)
(SECY) 2.
The Comission discussed Emergency'. Response Procedures without reaching a final decision.
3.
The Comission agreed to finalize and dispatch a letter to Mr.
Janes J. O'Connor, Chairman, Comonwealth Edison Company, concerning the licensing schedule for the Byron Nuclear Station.
ENCLOSURE M
l J I.
STAFF REQUIREMENTS - AFFIRMATION SESSION 81-26,_2:15 PM, MONDAY, JUNE 29, 1981, COMMISSIONc.RS CONFERENCE ROOM, DC 0FFICE (OPEN TO PUBLIC ATTENDANCE). Memo SECY to Dircks/Bickwit, dtd 6/30/81.
I.
SECY-81-373 - PROPOSED ADDITION TO THE SECRETARY'S AUTHORITY TO RULE ON MISFILED PLEADINGS UNDER 10 CFR 2.772 (Rulemaking 1ssue)
The Commission, by a vote of 4 -0*, approved for publication in the-Federal Register an amendment to 10 CFR 2.772 to permit the Secretary to issue orders, without Commission af firmation, to redirect pleadings erroneously filed by the Commission to the appropriate board.
All Commissioners agreed with the modifications proposed by Commissioners Gilinsky and Ahearne.
(OGC)
(Subsecuently, the Federal Register Notice was signed
~
~~
by the Secretary.)
Section 201 of the Energy Reorganization Act, 42 U.S.C.
E5841, provides that action of the Commission shall be determined by a " majority vote of the members present."
Co amissioner Ahearne was'not present when this item was aifirmed, but had previously indicated that he would approve this item.
Had Commissioner Ahearne been present, he would have affirmed his prior vote.
Accordingly, the formal vote of the Commission was 3-0 in favor of the amendment.
II.
SECY-81-335 - 10 CFR PART 61
" LICENSING REQUIREMENTS FOR LAND DISPOSAL'OF RADIOACTIVE WASTE" (Rulemaking Issue)
The Commission, by a vote of 3-0* approved for publication in the Federal Register, as modified by Commissioner Bradford's memo of 6/25/81, a proposed rule on Licensing Requirement for Land Disposal of Radioactive Waste.
The modification at page 85, subsection 5, should read as follows:
" (5)
Waste must not.contain, or be capable of generating, quantities of toxic gases, vapors, or fumes harmful to persons transporting, handling, or disposing of the waste."
(NMSS)
(SECY Suspense:
7/17/81)
Section 201 of the Energy Reorganization Act, 42 U.S.C.
85841, provides.that action of the Commission shall be determine ~d by a " majority vote of the members present."
Commissioner Ahearne was unavailable to participate when this item was affirmed.
Accordingly, the formal vote of the Commission was 3-0 in favor of the proposed modification.
ENCLOSURE M
,.. I.
(Continued')
The commission also approved:
a.
staff's conclusions set forth in Enclosure B, which provides the analysis called for by the Periodic and Systematic Review of the Regulations.,
(NMSS)
(SECY Suspense:
7/17/81) b.
a certification that the rule will not have a significant economic impact on a substantial number of s, mall entities.
(ADM)
The Commission requested that:
a.
a Draft Environmental Impact Statement will be published concurrently with the approval of the publication of the proposed rule.
(NMSS)'
(SECY Suspense:
7/17/81) b.
a detailed staff analysis of public comments on the Advance Notice of Proposed Rulemaking be contained in the Draft Environmental Impact Statement.
j (NMSS)
(SECY Suspense:
7/17/81) c.
appropriate Congressional Committeer be inforn. a.
(OCA/NMSS)
(SECY Suspense:
7/17/81)
J.
STAFF REQUIREMENTS - CONTINUATION OF DISCUSSION AND POSSIBLE V0 LICENSE FOR MCGUIRE, 2:30 PM, MONDAY, JUNE 29, 1981, COMMISSIONERS CONFERENCE ROOM, DC 0FFICE (CLOSED TO PUBLIC ATTENDANCE).
Memo for the Record fm SECY, dtd 6/30/81.
The Comission, by a vote of 4-0*, approved an order authorizing the Director, ilRR, to issue a full-power operating license for McGuire-i.
All Cocnissioners indicated they would attach separate views.
(Subsequently the Secretary signed the Order.)
I
- Section 201 of the Energy Reor~ganization Act, 42 U.S.C. 15841, provides that action of the Consnission,shall.be determined by a " majority vote of the members 'present."
Comissioner Ahetene was not present when this item was approved, but had previously indicated.his approval of the order.
Had Comissioner Ahearne been present, he would have affirmed his prior vote.
Accordingly, the formal vote of the Comission was 3-0 in favor of t!
decision.
- ^