ML20058N388
| ML20058N388 | |
| Person / Time | |
|---|---|
| Issue date: | 01/27/1982 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| Shared Package | |
| ML20058M131 | List:
|
| References | |
| FOIA-92-436 SECY-82-036, SECY-82-36, WIR-820122, NUDOCS 9310140231 | |
| Download: ML20058N388 (29) | |
Text
...
UNITED STATES i
NUCLEAR REGUI.ATORY COMMISSION l
WASHINGTON, D. C. 20555 1.
aenuay 27, 1982 INFORMATION REPORT SECY-82-36 For:
The Commissioners i
From:
T. A. Rehm, Assistant for Operations, Office of the EDO
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING JANUARY 22, 1982 I
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 dperational Data K
Small & Disadvantaged Business Utilization L*
j Items Approved by the Commission M*
i DISTRIBUTION
^
Commissioners y
ission Staff Offices T. A. Rehe;-Asst!!fant for Operations Office of the Executive Director Secretaria:
for Operations h
';]
- No input this week.
Contact:
9310140231 930218 FOR INTERNAL NRC 7_
T. A. Rehm, EDO
$$[y9909$-436 DISTRIBUTION ONLi (h
)
PDR 49-27781
/
04.qt -//d S
(
~
l
()-Y d 5 1 -3 6 c
SUMMARY
OF WEEKLY INFORMATION REPORT Week Ending January 22, 1982 i
Results of a weekly surveillance flow test conducted on January 14, 1982, showed that Asian clams were found in Loop II of the Service Water System, particularly in the containment fan cooler heat exchangers. This is apparently a continuation of the clam rroblem first encountered at ANO in September 1980, which prompted l
issuance of r IE bulletin to all licensees.
l i
Virgil C. Summer j
On January 20, 1982, the ASLB held hearings to discuss emergency planning. At the conclusion of that session the Board closed the record on all contentions.
The ASLB decision date currently projected in the Bevill schedule is April 1982.
BWR Ooeratina Reactors with Mark I Containments
]
The Commission issued Orders to the above plants granting extensions of the exemptions and extending the completion dates for installation of plant modifications needed to comply with the staff's Acceptance Criteria contained i
in Appendix A to NUREG-0661. The granting of the extension is based on unforeseen difficulties and delays identified by the licensees.
TMI-1 Restart On January 7, 1982, the U. S. Court of Appeals for the District of Columbia ruled
)
that the NRC should consider psychological. stress as a TMI Unit i restart issue.
l The NRC has made no decision regarding possible legal appeals.
Advance Notification to Governors: Final Rule i
On January 6,1982, the NRC published its final rule requiring NRC licensees to provide advance notification to governors before making shipments of irradiated reactor fuel. The rule becomes effective on July 6, 1982.
i Significant Enforcement Action The NRC fined Boston Edison Co. (Pilgrim) $550,000 based on a series of alleged management problems associated with engineering reviews, revisions to operating procedures, plant maintenance, plant modifications, notifications to the NRC, j
and the company's safety committee's activities.
i f
OFFICE OF ADMINISTRATION Week Ending January 22, 1982 l
ADMINISTRATION OF THE FREEDOM OF INFORMATION ACT l
STATUS OF REQUESTS Initial Appeal of Recuest Initial Decision i
~
Received 46 4
Granted 13 0
l Denied 2
1 Pending 31 3
i ACTIONS THIS WEEK i
Received i
Robert Nelson, Requests four categories of documents regarding Los Angeles Federation radioactive vastes disposed of by the Atomic of Scientists Energy Project at UCLA.
(82-10)
Robert Nelson, Requests 11 categories of documents regarding the Los Angeles Federation disposal of radioactive wastes on the property of of Scientists the Veterans Administration in West Los Angeles.
(82-11)
Scott Schulke Requests a listing of all licensed non-commercial (82-12) nuclear reactors in the U.S. and a listing, by location, of all NRC licensed low-level and high-level radioactive waste dumps throughout the U.S.
l Lynn Connor, Requests a copy of Revision 4 of the Westinghouse Doc-Search Associates Standard Technical Specifications (NUREG-0452).
(82-13)
Stephen A. Wachter Requests all documents between General Public (82-14)
Utilities / Metropolitan Edison and the NRC regarding the restart of Three Mile Island, Unit 1, from March 1979 to the present.
Joan A. Estrada, Requests copies of invoices for all carpet Professional Carpet installation, repairs, and soil extraction for Service November and December 1980 and December 1981.
(82-15)
CONTACT:
J. M. Felton 492-7211 ENCLOSURE A-t
2
~
Received, Cont'd Ruth E. Van Demark, Requests specific records on nuclear power plants Wildman, Harrold, in Illinois for which Comonwealth Edison is the Allen & Dixon licensee.
(82-16)
(An individual requesting Requests information on his Reactor Operator information about himself)
License examination results.
(82-17)
(NRC employee}
Requests a copy of the Candidate Evaluation, (82-18)
Certification and Selection Record (CERT) for Vacancy Announcement No. 82-0429.
Granted Lawrence Coe Lanpher, In response to a request for records which relate Kirkpatrick, Lockhart, to the evaluation of emergency operating Hill, Christopher &
procedures at the Diablo Canyon Nuclear Power Phillips Plant by the Xyzyx Infomation Corporation, (81-517) made available one document. Informed the requester additional documents subject to this request are already available at the PDR.
A. V. Eggers, In response to a request for a copy of the Earth Science winning proposal under Request for Proposal Consulting and RS-NMS-82-028, made available copies of non-Technology, Corp.
proprietary versions of technical proposals i
(S2-2) for the three awarded contracts.
Lynn Connor, Made available a copy of Revision 4 to NUREG-0452.
'oc-Search Associates Standard Technical Specifications for Westinghoust (82-13)
PWRs.
Denied i
(NRC employee)
In response to a request for six categories of (81-518) information pertaining to Vacancy Announcement No. 81-4349, made available eight documents.
Denied portions of five documents, the disclosure of which would constitute a clearly unwarranted j
invasion of personal privacy.
l ENCLOSURE A l
DIVISION OF TECHNICAL INFORMATION AND DOCUMENT CONTROL
- Translations Completed for the Period Ending December 31, 1981 Copies of these translations will be available in the Library on Microfiche for internal NRC staff use only.
These translations are derivative works created from foreign documents by the foreign author and are still the property of the forcion author or spon-soring government.
GERMAN Translation 919 A, B.
C, D
PROPRIETARY GRS-A- 4 80 ( 919 A), GRS-A509 (919B1, GRS-A-540 (919C), and GRS-A-55B(919D)
Unusual Occurrences in Nuclear Power Plants of the Federal Republic of Germany - Four Quarters of 1980.
H.
J.
i Herrman, Reactor Safety Corporation.
July 1980.
Cologne, Federal Republic of Germany.
50 pages.
Requested by: J. D. Lafleur, OIP.
l Cost: $2000.00.
l Translation 947 Fracture of a Feedwater Pipe with Nonreturn Valve.
T.
Grillenberger (Tu Hunich), D.
L.
Nguyen, W. Winkler.
- Garching, Federal Republic of Germany.
June 1981.
188 pages.
Requested by:
S.
Fabic, RES.
Cost: 5425.00.
1 FRENCH Translation 959 The Reprocessing of Irradiated Fuels in France.
Commissariat a l'Energie Atomique, Paris, France.
September 1981.
147 pages.
Requested by: J.
Lafleur.
Cost: $2,500.00.
JAPANESE I
i Translation 948 I
Results of Regular Inspection.
M.
Kamimura.
Overseas Electrical l
Industry Survey Institute, Washington, D. C.
August 1981.
8 pages.
Requested by:
J. Lafleur, IP.
Cost: S70.00.
Translation 949 Operation Report.
Fiscal 1981, from April to August 1981.
M. Komimura.
Overseas Electrical Industry Survey Institute, Washington, D.
C.
April 1981.
15 pages.
Requested by:
J.
Lafleur, IP.
Cost $100.00.
"This cocplete TIDC entry is deleted from the PDR copy.
ENCLOSURE A I
I
h 2
Translation -
December 31, 1981 i
i SPANISH Translation 961 PROPRIETARY Appendix - Incidents at Santa Maria de Garona NPP.
Junta de Energia Nuclear, Madrid, Spain.
1981.
5 pages.
Requested by: J. Lafleur, IP.
Cost: $40.00.
SWEDISH Translation 950 Quarterly report from the State Nuclear Power Inspectorate, April-June 1981.
State Nuclear Power Inspectorate.
Stockholm, Sweden.
April-Jur.e 1981.
20 pages.
Requested by:
J.
- Lafleur, IP.
Cost: 5170.00.
1 i
Documents Processed By Policy and Publications Management Branch Division of Technical Information and Document Control Number of fiUREG reports printed and/or distributed by TIDC in December 1981.
Number Processed Tyoe of Report in December j
Draft Environmental Statement 6
Final Environmental Statement 0
l Safety Evaluation Report 3
i i
Environmental Standard Review Plan 0
i NRCI's 0
i Staff Reports (total combined figure) 22 Contractor Report 50 Conference Proceeding 0
Brocnures 0
TOTAL = 72 1
l A listing of these NUREG reports is contained in " Regulatory and Technical Reports Compilation" (NUREG-0304), issued quarterly and available from TIDC.
ENCLOSURE A i
t i
l
DIVISICN OF CXITTR; CTS Week of January 22, 1982 l
l 1
i CCNTRICES CIDSED OUT (All WinieJative action mleted and fM ppt made) j CCNTR7CT 10.
CXNTRAC'IOR NN-OLTf-DATE i
1 NRC-10-76-334 Federal Prison Industries 1/13/82 i
NBC-ll-81-427 Dr. Pierre Zaleskd 1/19/82
.l l
4 i
I 1
ENCLOSURE A r
r l
"~
~~~
OFFICE OF NUCLEAR REACTOR REGULATION WEEK ENDING JANUARY 22, 1982 Operator Licensina During the month of December 1981 the Operator Licensing Branch issued 36 new Reactor Operator Licenses and 16 new Senior Reactor Operator Licenses.
These' licenses were issued to personnel at 17 facilities. In addition, the l
OLB issued 10 renewal Reactor Operator Licenses and 29 renewal Senior Reactor Operator Licenses.
These licenses were issued to personnel at 10 facilities.
Arkansas Resultsofaweeklysurveillanceflowtestcon'ductedon1/14/82showeddat Asian clams were found in Loop II of the Ser_vice Water System, pa"ticularly in the containment fan cooler heat exchangers.. This is significant because it is apparently a cc:itinuation of the clam problem which was first encountered at AND in September 1980, which ' prompted issuance of an IE Bu11etin'(81-03)
- to all licensees.
/
Abcut 5 gallons of clams,1/2-5/8' inches in diameter, were removed by hand from.the fan coolers. The licensee has not determined if these were survivors.
from previous irrvasions or had recently entered the system..Numefo'us oth'er pump-and room ccolers were checked and found to have only small quantities of clams. All affected coolers were verified by testing or i.nspection to be. operable prior to being returned to service.
MO*iTICELLO NUCLEAR GENEPATING PLANT Morticello returned to power operation on January 17, 1982 after an 86-day major modifications / maintenance outage which began October 24, 1981.
Activities performed during the outage included: Mark I long Term l
I program torus modifications; feedwater sparger modifications; certain l
TMI modifications; and preventive maintenance on the 4ky electrical system, feedwater pumps, and recirculation pumps.
I l
Restart was initially scheduled for the first week of Decemb' r 1981.
e l
However, delays were encountered due to turbine disc cracking problems; replacement of core spray piping between reactor vessel and first maintenance valve based on ISI indications; shutdown cooling system valve disc replacement; and severe cold weather.
i The next refueling outage is scheduled for June 19E2.
ENCLOSURE E
l
~
~
Viroil C. Summer Nuclear Station On January 20, 1982 the ASLB held hearings to discuss emergency planning.
At the conclusion of that session the Board closed the record on all contentions. The ASLB decision date currently projected in the Bevill i
schedule is April 1982.
~BWR Operatine Reactors with Mark I Containments Co::nission Orders have been issued modifying the existing (Order datesCooper N for 21 of the 22 cperating BWRs with Mark I Containments Station will meet the existing order date). These Orders grant extensions i
of the exemptiens and extend the completion dates.for installation of plant roodifications needed to comply with the staff's Acceptance Criteria contained '
in Appendix A to NUREG-0561.
1 The granting of these extensions is based on unforeseen difficulties and delays identified by the 1.icensees primarily related to one or.more of l
the following:
{1) torus and torus attached piping analyses; (2) equipment j
delivery; (3) the use of interpretations a,nd/or alternate approaches to the -
NUREG-V561 Acceptance Criteria;- (4) plant-unique design and modification.-
problems; and (5) slippages in refueling outages.
(
Meetinc Suoject:
Meeting with Westinghouse Owners' Group Representatives and f
Westinghouse on Emergency Operating Procedure Technical l
Guidelines (
Reference:
TMI Task Action Plan Item I.C.1) l i
.Date/ Time:
February 9, 1982, 9:00 AM Location:
Air Rights Bldg., Room 4550 Montgomery Ave., Room 5033, Bethesda, MD Attendees:
Westinghouse, Westinghouse Owners' Group, Brent Claytoti is NRR conta j
Summary of January 15, 1982 CRBR Review Meeting A meeting was held on January 15, 1982 in Bethesda, Md. to discuss sodium-l concrete reactions. The applicant described the results of all sodium-concrete interaction test data to date. Twenty-two sodium-concrete tests were reviewed.
I The test results varied grer.tly. Specifically, the total concrete penetration ranged from zero to seven and one-hs1f inches. The penetration rates also varied from zero to ten inches per hour. However, the high penetration rates were short-lived.
The applicant then discussed the sensitivity of high concrete penetration rates on the containment integrity and radiological doses. The results, although still preliminary, show that containment integrity is maintained and that offsite doses are within 10 CFR 100 limits.
The applicant then described their plans to conduct additional sodium-concrete interaction tests in an effort to obtain more test data and to better understand sodium-concrete phenomenology.
ENCLOSURE B f
. I
6 b
j NRC TMI PROGRAM OFFICE WEEKLY STATUS REPORT r,
J I
January 17, 1982 - January 23, 1982 i
Plant Status Core Cooling Mode: He'at transfer from the reactor coolant system (RCS) l loops to reactor building ambient.
Available Core Cooling Modes: Decay heat removal systems. Long term cooling "B" (once through steam generator-B).
RCS Pressure Control Mode: Standby pressure control (SPC) system.
Backup Pressure Control Modes: Mini decay heat removal (MDHR) system.
Decay heat removal (DHR) system.
Major Parameters (as of 0500 January 22,1982) (approximate values)
Average Incore Thermocouples : 106*F l
Maximum Incore Thenncoupie:
134'F I
RCS Loop Temperatures:
A B
Hot Leg 98'F 101'F 74*F 83'F Cold Leg ((1) 2)
75'F 89'F RCS Pressure : 96 psig Reactor Building: Temperature :
58'F i
I Water level:
Elevation 285.2 ft. (2.7 ft, from floor)
Pressure:
-0.5 psig
[
l Airborne Radionuclide Concentrations:
1.5 x 10-5 uCi/cc Kr 85 3.6 x 10-7 uCi/cc H3 (samples taken 1/24/82)
Effluent and Environmental (Radiolacical) Information l
1.
Liquid effluents from the TMI site released to the Susquehanna j
River after processing, were made within the regulatory limits and in accordance with NRC requirements and City of Lancaster Agreement l
dated February 27, 1980.
During the period January 15, 1982, through January 21, 1982, the effluents contained no detectable radioactivity at the discharge point although individual effluent sources which originated within Unit 2 contained minute amounts of radioactivity. Calculations indicate that less than one millionth (0.000001) of a curie of I
cesium was discharged.
ENCLOSURE B i
2.
Environmental Protection Agency (EPA) Environmental Data. Resul ts from EPA monitoring of the environment around the TMI site were as follows :
3 f
The EPA measured Kr-85 concentrations (pCi/m ) at several environmental monitoring stations and reported the following results :
Location December 4 - December 28, 1981 (pCi/m4)
Gol ds bo ro 22 Observation Center Middletown 23 I
Yorkhaven 31
- Results not available at time of this report.
All of the above levels of Kr-85 are considered to be background levels.
No radiation above normally occurring background levels was detected in any of the samples collected from the. EPA's air and gamma rate networks during the period from January 13, 1982, through January 21, 1982.
3.
NRC Environmental Data. Results from NRC monitoring of the environment arouno 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 Samole Period (uti/cc) (uCi/cc)
HP-303 January 13, 1982 - January 20, 1982
<6.1 E-14 <6.1 E-14 4
Licensee Radioactive Material and Radwaste Shipments.
On Tuesday, January 19, 1982, one drum containing radiation monitor HPR-212 (retrieved from the Unit 2 reactor building during entry no. 20) was shipped to Sandia National Laboratory, Albuquerque, New Mexico.
~
On Wecnesday, January 20, 1982, one drum containing twelve, 1-foot sections of Unit 1 steam generator tubes was shipped to Babcock and Wilcox (B&W), Lynchburg, Virginia.
ENCLOSURE B i
. On Wednesday, January 20, 1982, one drum containing eight, 1-foot sections of Unit 1 steam generator tubes was shipped to Battelle-Columbus Laboratory, Columbus, Ohio.
20, 1982, two, one liter samples from On Wednesday, January the Unit 2 spent fuel pool (submerged demineralizer system) were shipped to Babcock and Wilcox (B&W), Lynchburg, Virginia.
21, 1982, 60 drums of Unit i and Unit 2 On Thursday, January l
contaminated laundry were shipped to Tri-State Industrial l
Laundries, Utica, New York.
Major Activities Processing of batch 17 1.
Submerced Demineralizer System (505).Dut processing was immediately 20, 1952, comentec on January secured when a process train leak into the spent fuel pool water The SDS process train is 1ccated underwater in the was detected.
Unit 2 spent fuel pool. Plant monitors showed no increase in On January.23,1982, it was effluents as a result of the leak.
l l
determined that the cause of the leak was a worn gasket which seals the connection between the system piping and the ion exchange ves sel s.
The gasket was replaced and the subsequent leak check was satisfactory.
The raditactivity in the spent fuel pool water increased fron approximately 1 x 10-4 uc/ml (gross S-y activity) to 7 x 10 b c/ml.
u The increase does not affect the health and safety of workers in the vicinity of the spent fuel pool and therefore will not interrupt processing of water through the SDS. Processing of batch 17 recommenced on January 23, 1982.
i The licensee plans to install a supplemental cleanup system to improve the rate of radionuclide removal from the spent fuel pool.
2.
EPIC 0p. _II.
The Ep1COR II system was shutdown during the week because tne 505 nas not been operating.
3.
Reactor Buildina Entries. There was no work performed inside the i
reactor ouilcing (RB) tnis week. Two RB entries have been scheduled I
i for the last week in January. The tasks scheduled for the next two entries include video taping of certain areas of the RB, I
acditional work on the NI-2 neutron monitor, and load testing of crane mounted supports for the power lift.
Supporting activities for the gross decontamination experiment have not been completed and the commencement date of the decontamination is not certain. The two major activities which need to be completed j
prior to the decontamination include the fabrication and installction i
of two modified flanges on a spare RB penetration and the installation of a power lift device which will be used between the refueling floor (3a7 ft. elevation) and the polar crane during the decontamination ex;eriment.
ENCLOSURE B I
I
1 I
r i -
.4.
Meetings Held On Tuesday, January 20, 1982, Lake Barrett met with the Lancaster County Southern End Affinity Group in the NRC Middletown office to discuss the status of Unit 1, the Unit 2 cleanup, and general nuclear topics. In addition to extensive discussions on the above topics, the group verbally emphasized their previous written requests to the NRC for local public hearings or meetings with the NRC Commissioners to present their opposition to the restart of Unit 1.
Future Meetines 1.
The NRC's Advisory Panel for the Decontamination of TMI Unit 2 will meet on January 28,1982 from 7:00 PM to 10:00 PM at the Holiday Inn, 23 South Second Street in Harrisburg.
The meeting i
will be open for public observation. The Panel plans to discuss.
alternative strategies for assuring financial resources to complete the TMI-2 cleanup.
2.
On Friday, January 29, 1982, Lake Barrett will meet with the Middletown Mothers to. discuss TMI related issues in general.
3.
On Friday, February 25, 1982, Lake Barrett will be speaking for the dinner meeting being held by the Engineers Week Joint Planning Council to honor Lehigh Valley's Engineer of the Year and Young l
l Engineer of the Year.
4 On Saturday, March 13, 1982, Lake Barrett will address the Society f
of Manufacturing Engineers in Williamsport, PA, on the cleanup of TMI and general aspects of nuclear power.
i l
l 1
ENCLOSURE B l
1
- S-TMI Unit 1 Develooments_
On January 7,1982, the US Court of Appeals for the District of l.
Columbia r'uled that the NRC should consider psychological stress as a TMI Unit I restart issue. The court ruling is attached. The NRC l
has not received the written opinion of the two judges that ruled i
that the NRC must consider psychological stress as a restart issue.
I Consequently, the NRC has made no decision regarding possible legal appeals.
i On February 4 and 5,1982, the NRC staff will sponsor a meeting in I
l 2.
the Mitre Corporation offices in McLean, Virginia, of approximately l
13 professional psychiatrists, psychologists, and research experts I
to obtain their advise on how to access the psychological stress that may be caused by the restart of Unit 1.
The upcoming meeting was announced in a meeting held on January 22,1982, in Bethesda,
(
j Maryland, between the NRC staff, People Against Nuclear Energy (PANE) and General Public Utilities (GPU).
i I
I l
l l
l i
t I
i ENCLOSURE B i
RetypedintneTMi?Lj t
No. El-1131 7
i Filed: January 7,1982
?ec:le Against Nuclear Energy, Fe:itioner v.
I Unite: States Nuclear Regulatory Co= mission and United States of America, Respondents l
Me:rocolitan Edison Company, et al.
j (Public Utilities), Intervenors j
Petition for Review of an Order of the United States Nuclear Regulatory Commission Before: WRIGHT, Circuit Judge, McGCWAN, Senior Circuit Judge, and WILKEY, Circuit t
Judge.
JUDGMENT t
4 This cause :ame on,to be heard on a petition for review of an order of the United 5:stes Nuclear Cc mission and was briefed and argued by counsel.
Cn consideration thereof, it is CRDERED and ADJUDGED by this c urt that the order I
of ne Nuclear Regulat:ry C mission under review in this cause is hereby vacated.
It is FURTHER ORCERED and ADJUOGED by this court that the Cc==ission shall prepare an envir:n= ental assessment regarding the effects of the prooosed restart of the i
nuclear facility at Three Mile Island Unit.One (TMI-1) on the psychological health of neightcring residents and on the well-being of this surrounding :::= unities.
The C ::ission shall then determine, on the basis of this envir:n= ental assessment, whether the National Envir:nmental Poldcy Act requires preparation of a full environmental impact statement.
It is FURTHER CRDERED and ADJUDGED by this courst that, until the Ccemission has
~
c::: lied with the re:uirements of the Natienal Environmental Policy Act as
- escribed in the preceding paragraph, it shall not make a decision t: restart n..-i.
It is FURTHER CRCERED and A00UCGED by this court that the C ::ission shall
- re:are a statement of the reasons for its determination that psychol:;ical r.eal:n is n:: ::gni:aale under tne A::mic Energy Act.
Opinions to follow.
Per Curia:
For the Cour
/s/
George A. Fisher Cl erk Circuit Judge W'LKEY dissents. Whether designedly so or not, this Order will bar -te resumpti:n of furnishing nuclear ;cwer from TMI-1, at wni:5 there has never been an accident, until such time as the Nuclear Regulatory C:::issien sa: sfies this ::urt, firs: by an " environ =en al assessment," and -hen :os:
likely, later by a require: " full environmental 1 :a:: statemen*," as *: i*s
- nsicera-ion of certain new environmen a'. fa:::rs. This delay is i :csed because Of ite asser:a: ' :ac
":n he :sychc10;ical health of neightering residents,'
en "it:at:" wnica has ever before been c:nsi ered as ::vered by -ne Nati:nal Envirenzen:31 ;;1fcy *::.
ENCLOSURE B 9
i 2.
- o 81-1131 - People Against.'iuclear Energy v. USRNC This is yet another examole of a court inventing new procedural recuirements er an administrative agency in a matter which has enormous substantive consequences.
The court ~
(See Vermont Yankee Nuclear.ower Coro. v. NRDC, 435 U.S. 519 (1978).
c t
is concernec tna ":ne weni-ceing or tne surrounding communities" be assessed, yet while this is taking place, for the co=munities near TMI-1 it will be a colder winter than predicted.
l 1
{
l l
l
?
l l
~
4 1
I l
1 ENCf.05URE B l
i l
f l
I I
Y OFFICE OF NUCLEAR HATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending January 22, 1982 Revision to Appendix A of Regulatory Guide 10.8 NMSS has scheduled a Federal Register notice for publication on January 22 to provide public notice of a proposed revision to Appendix A of Regulatory Guide 10.8.
Appendix A concerns training and experience criteria for physi-cians who apply for authorization to use byproduct material in medical diag-nosis and therapy. The proposed revision is based upon recommendations from NRC's Advisory Committee on the Medical Uses of Isotopes (ACMUI) and from various professional groups including the Federated Council of Nuclear Medi-cine Organizations. Since the beginning of 1980, the ACMUI has held three public meetings on this subject.
Advance Notification of Governors: Final Rule On January 6,1982, a final rule requiring NRC licensees to provide advance notification to governors before making shipments of irradiated reactor fuel was published in the Federal Register. The rule will become effective on July 6, 1982.
U.S./ Canadian Safeguards Technical Exchange On January 12-13, a representative from NMSS participated in a U.S./ Canadian technical exchange of information on the application of IAEA safeguards to CANDU on-load reactors. Representatives from ACDA and the State Department also participated in the meeting which included visits to the Douglas point and the Bruce reactors in Canada. A reciprocal visit to the U.S. is planned later in the year.
i l
l
(
ENCLOSURE C l
I
Division of Safeguards - Planned Meetings 1.
Subject:
Briefing on Technical Assistance re International Safe 9uards Date:
January 29, 1982
)
location: Willste Bldg.
Attendees: Anthony Fainberg, BNL Allen Brieber, BNL Ken Sanders, SG 2.
Subject:
Mtg with Dr. Alexander Robnagel of Gemany to discuss long tem context of nuclear terrorism Date:
February 4,1982,1:00 p.n.
Location: Willste Bldg. - Mr. Burnett's office Attendees:
R. F. Burnett G. W. McCorkle 3.
Subject:
Mtg with V. C. Sumer to discuss preoperation inspection issues at the site Date:
January 28-29, 1982 Location: Columbia, S. C.
l Attendees: Region II inspectors:
David Moore Rocer Goode Dale Kers, SGRL 4.
Subject:
Mtg. at Bellefonte to discuss security plan and site visit l
Date:
January 25-27, 1982 Location: Scottsboro, Alabama l
Attendees: TVA representatives l
IE Region 11 representatives I
C. Gaskin 5.
Subject:
Visit Florida Power to review plan changes to Crystal River Date:
January 28-29, 1982 Location: Crystal River, Florida Attendees:
C. Gaskin K. McConnell 6.
Subject:
Visit to Kansas Gas & Electric, Molf Creek for initial site visit Date:
February 1-4, 1982 l
Location: Kansas I
Attendees:
D. Kunze l
ABSENCES OF THE DIRECTOR On DEPUTY DIRECTOR January 28 & 29, 1982 - Robert F. Burnett Acting: Richard Granann Donald R. Chapell ENCLOSURE C i
l z
i I
t f
Meetinos - Division of Fuel Cycle and Material Safety j
I 1.
Subject:
Meeting with Nuclear Fuel Services, Inc., to discuss geological drilling at West Valley, New York.
Date/ Time:
January 22, 1982, 3:00 p.m.
Location:
NFS Corporate Headquarters, Rockville, Maryland Attendees:
Thomas F. Carter, Jr. and A. Thomas Clark (FC) and Representatives of NFS and ESBR.
2.
Subject:
Meeting with United Nuclear Corporation to discuss decommissioning of the Wood River Junction-Facility.
Date/ Time:
January 26, 1982, 1:00 p.m.
Location:
Fifth Floor Conference Room, Willste Building, SS Attendees:
R. E. Cunningham, T. F. Carter, Jr., R. G. Page, W. T. Crow (NRC); J. Roth (R:I) and Representatives of UNC.
3.
Subject:
Meeting with Combustion Engineering to discuss license renewal application and discuss shortcomings in responses and schedule for obtaining required information.
Date/ Time:
January 27,1982,10:00 a.m.-4:00 p.m.
Location:
8th Floor Conference Room (a.m.) and 5th Floor Conference Room (p.m.), Willste Building, SS Attendees:
N. Ketzlach and A. L. Soong (FC), J. Roth (R:I) and Representatives of Combustion Engineering.
i ABSENCES OF DIRECTOR OR DEPUTY DIRECTOR January 28-30, 1982 Richard E. Cunningham and Thomas F. Carter, Jr.
Attending the NMSS Management Seminar in Harper's Ferry..WV.
William T. Crow will be Acting Director, FC, during their absence.
ENCLOSURE C I
-~ - -
4 Meetings - Division of Weste Management None Absences of the Director / Deputy Director John B. Martin, Director, WM, and Robert E. Browning, Deputy Director, WM will both be absent while attending the NMSS Management Meeting on January 28 and 29, 1982. John J. Sumeier, WMPI, will be acting for John B. Martin.
)
i I
ENCLDSURE C I
L
i i
i i
a OFFICE OF INSPECTION AND ENFORCEMENT Items of Interest l
January 18, 1982 to January 22, 1982 1.
Significant Enforcement Actions:
a.
Boston Edison Co. (Pilgrim) - On January 18, 1982, a Notice of Violation and Proposed Imposition of Civil Penalties in the amount of 5550,000 and an Order Modifying License effective imediately were issued to Boston Edison Company M/C Nuclear, Boston, Massachusetts. This action is based on a series of alleged management problems associated with engineering reviews, revisions to operating procedures, plant maintenance, plant modifications, notifications to the NRC, and the company's safety committee's activities. The licensee has 30 days from the date
~
of the Notice in which to respond.
j 2.
Preliminary Notifications relating the following actions were dis-patched during the week:
a.
PNO-I-82-03, Consolidated X-Ray Service - Lost Radiography Source.
b.
PN0-I-82-04, United States Priority Transport Corp. - Loss of Radioactive Material by Vehicular Theft.
c.
PNO-I-82-05, Vermont Yankee Nuclear Po er Corp, Yankee Atomic w
Electric Co. - Seismic Event.
j d.
PNO-I-82-06, Duquesne Light Company (Beaver Valley) - Spill of i
Low Level Radioactive Waste Inside the Protected Area.
e.
PNO-I-82-07, General Public Utilities Nuclear Corp (0yster Creek) -
Extended Shutdowns.
f.
PNO-I-82-08, Power Authority State of New York - Transport of Contaminated Injured Person to Offsite Hospital.
g.
PNO-II-82-08, Nuclear Fuel Services, Inc., (Erwin) - Reported Inventory Difierence.
h.
PNO-II-82-09, Drolina Power and Light Co. (Brunswick Unit 2) -
Inoperable RHR Service Water Subsystems.
i
- i. PNO-II-82-10, Carolina Power and Light Co. (Harris Units 1 & 2) -
d Media Interest in Emergency Plans.
- j. PHO-II-82-11, Tennessee Valley Authority (Sequoyah Unit 1) - Trans-former Failure and Oil Fire.
k.
PNO-II-82-12 Tennessee Valley Authority (Sequoyah Unit 2) - Unit Trip and Safety Injection.
1.
PN0-III-81-119A, Comonwealth Edison Co. (Zion) - Alleged Suppression of Drug Use Information by Licensee, Update.
m.
PNO-III-82-07, University of Michigan - Iodine-131 Release to i
Unrestricted Area.
n.
PNO-III-82-08, Illinois Power Co. (Clinton Station) - Stop Work Order - Electrical Construction.
o.
PNO-III-82-09 & 9A, Commonwealth Edison Co. (Quad-Cities Unit 2) -
Crack in Isolatable Portion with Reactor Water Cleanup System Inside Dry Well.
ENCLOSURE D f
1-1 i
p.
PNO-III-82-10, Commonwealth Edison Co. (Dresden) - Unplanned Release I
of Radioactive Material and Personnel Contamination In-Plant.
i q.
PNO-V-82-05, Southern California Edison Co. (San Onofre Units 2 & 3) -
Independent Design Verification.
r.
PNO-V-82-06, General, No Specific Facility Involved - Posting of Radioactive Warning Signs in Public Domain, s.
PNO-TMI-82 Metropolitan Edison Co. (Three Mile Island Unit 2) -
Leak from Borated Water Storage Tank (BWST).
l l
l l
l l
l ENCLOSURE D f
h I
i l
OFFICE OF NUCLEAR REr,ULATORY P.ESEAPCH
[
IMPORTANT EVENTS F0D THE WEEK ENDINC JANUARY 22, 1982 i
1 l
Experimental Procrams Branch
{
1.
Data Bank I
Three new PBF tests from the Gap-Conductance Test Series were added to the data bank: GAP CON 2-1, 2-2 and 2-3.
i i
2.
LOFT
~
f The F1 pressurized center fuel assembly has been installed and the reactor vessel head replaced. All refueling related work is The problems with removal of j
expected to be finished next week.
one of the two downtomer instrument assemblies have resulted in a The full impact on the L9-3 ATWS test date i
two week schedule slip.
i is still being assessed and will not be available until next week.
The safety analysis staff and the test procedures staff have worked i
through the ATWS test plans and agree that the test can be perfomed i
safely and will meet all test objectives.
,4 3.
Small Business Contractors Workshop i
Representatives of the EPB, Andy' Hon and Jose Reyes, participated j
in the NRC Workshop for Small Business Contractors in High Technology Areas. They interviewed 23 firms to determine their areas ofOverall,
]
expertise and how they could best meet EPB research needs.
j a wide variety of useful skills were found to be available through
)
the small business program at greatly reduced contractual requirements.
r s
4.
Semiscale j
5 Test IB-1, a 100 percent comunicative cold leg break, was conducted I
on January 14, 1982. No oscillatory behavior was observed. Vicual l
observation of the break established that no liquid was passed U
during reflood.
A peak temperature of 1600 F was reached during l
reflood at approximately 300 seconds after break initiation. (EM type assumptions were used for safety injection times and flow rates.)
An 50 (System Operational) type test to duplicate the S-07-6 200 percent break is planned for approximately January 22, 1982.
A new test series to cover feed line and steam line breaks was authorized in response to the Mattson to Bassett memo of January 11, 1982.
A description of work proposed for pressurizer and candy cane separate effects testing has been received from Idaho in response to an NRC request for data to support reactor vessel thermal shock /
overpressure investigations. These topics will be discussed in detail with Idaho during the week of January 25, 1982.
ENCLOSURE E e
i 1
Analvtical Models Branch 1.
As part of the TRAC-PD2 and TRAC-BD1 i'ndependent assessment program. INEL completed the following reports:
1.
Post test calculations of Semiscale Tests 5-SB-2A and S-SB-4 with TRAC-PD2, EGG-CAAD-5702, December 1981.
l 2.
An Analysis of the Semiscale MOD-1 Test S-04-5 Using the TRAC-PD2/M001 l
Computer Program. EGG-CAAD-5706, December 1981.
3.
TRAC-pD2 Calculations of Semiscale Mod-1 Tests S-28-1 and S-28-10, EGG-CAAD-5707, December 1951.
Analysis of Semiscale Reflood Test S-07-4 Using TRAC-PD2, EGG-CAAD-4.
5699, December 1981.
l 5.
TRAC-BD1 Assessment Calculations for Marviken Tests 15 and 24 i
EGG-CAAD-5705, December 1981.
I 2.
A preliminary COBRA / TRAC calculation was performed by PNL to simulate a UHI-e:;uipped PWR plant with a 200 percent cold-leg break. A peak clad temperature of 1680cF was predicted during reflood.which appeared too high. Three problems were found in the code: (1) the initial stored energy of the fuel rods was too high because of an error in the gap conductance.nodel, (2) an Evaluation-Model decay heat curve was used in the calculation and it was about 20 percent higher than the ANS standard used for the best-estimate calculation, and (3) the dispersed flow heat transfer model of the code underpredicted the heat transfer during UHI delivery into the core.
Corrections will be made before the next calculation is performed in March 1982.
A letter was sent to Dr. M. Plesset of ACRS regarding this i
catter.
Transportation and Materials Risk Branch 1.
In accordance with Comission request for the week ending October 30, 1981 in connection with decisions on SECY-81-197/197A dealing with plutonium air snipments, RES has initiated an action to " consider whether there exist sufficient technical and policy bases for a staff recommendation to the Commission that NRC seek legislative relief for the air shipment of safeguards samples and other small quantities of plutonium for which rapid transport is needed and is of identifiable benefit to the public interest." The actio'n will consider the results of a DOE-sponsored study on whether the newly approved PAT-2 package, with its operational restrictions, will satisfactorily provide for shipment of safeguards samples. The task provides for a report to the Commission by July 15, 1982.
ENCLOSURE E e
1 i l 2.
In accordance with Commission request for the week ending October 30, 1981 in connection with decisions on SECY-81-197/197A dealing with plutenium air shipments, RES has evaluated "whether to encourage DOT to consider changes to existing DDT regulations that would reduce inconsistencies with the NRC regulations, as amended." Since all potential shippers of plutonium will be subject either to the Commission's rules in Part 71 or to the regulations of the Agreement States (the plutonium restriction is being made a matter of compatibility with the Agreement States) no control through DOT regulations is necessary, and no significant inconsistencies exist.
The RES staff plans no further action in this area.
Publications Issued During the Week of January 18-22, 1982 Reg. Guide 3.49 - Design of an Independent Spent Fuel Storage Installation (Water-Basin Type)
Reg. Guide 3.50 - Guidance on Preparing a License Application to Store Spent Fuel in an Independent Spent Fuel Storage Installation Forthcoming Speaking Engagement
Subject:
Robert B. Minogue will speak to the American Nuclear Society on the topic of NRC's Regulatory Research Program Date:
February 8, 1982 Location:
General Electric Research Center, Schenectady, NY i
l ENCLOSURE E
l ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING JANUARY 22, 1982 Senate Request Senator John Glenn has requested NRC response to several questions concerning the role of a U.S. firm in assisting South Africa to obtain enriched fuel for its Koeberg reactors. IP is drafting a response to the Senator.
Foreien Visits to NRC On Monday Ronald Anthony, Chief Iispector of the U.K. Nuclear Installations Inspectorate and John Dunster, Deputy Director General of the U.K. Health and Safety Executive, accompanied by Dr. John Gaunt Atomic Energy Attache at the British Embassy met with Chairman Palladino and Commissioners Gilinsky, Ahearne and Roberts as well as R. B. Minogue. Director of RES, H. R. Denton, Director of NRR, J. D. Lafleur, IP Deputy Director, R. Mills and F. Rowsome, RES, to discuss issues likely to impact on the U.K. PWR inquiry. On Tuesday they met with V. Stelle.
C. Rossi, NRR (integrated protective systems) and D. Rubinstein, NRR (PWR levr'. detector).
On Monday Mr. Haganaya, Member of the Standing Advisory Group for Nuclear Safeguards, and Mr. Otomo of the Japan Nuclear Fuel Services Company met with SG Director R. F. Burnett and members of his staff to discuss the application of nuclear safeguards and physical protection to reprocessing facilities.
On Wednesday Erik Green, Head of the Safety and Reliability Directorate of the United Kingdom Atomic Energy Authority, met with RES and NRR staff to discuss reliability data.
On Friday the new Economic Minister at the Korean Embassy in Washington, Mr. Chong Sang Park, made a courtesy call on Chairman Palladino.
Mr. Yoshindo Takahashi, Chief of Nuclear Fuel Section Tokai Research Establish-ment, and Mr. Masayuki Sato, Chief, JMTR Project, 0arai Research Establishment, have scheduled a visit to IP for January 27 to discuss delays being encountered in the conversion of Japanese research reactors from highly enriched uranium to the use of lower enriched uranium and to explain the Japan Atomic Energy Research Institute's request for additional HEU for the JMTR reactor.
l ENCLOSURE G f
f Foreien Reports i
The following foreign reports were received in IP January 18-22:
)
(For further information contact Eva Szent-Ivany, IP, X27788.)
j From Canada:
The Nature of Reactor Accidents **
From Finland:
Quarterly Report - April-June 1981**
From the FRG:
I PROPRIETARY GRS-A-635 TREBIL - A Computer Code for Fault Tree Preparation GRS-A-639 The Program System RALLY to Compute the Reliability of Larger Technical Systems - PROPRIETARY t
{
i
)
P Deleted from PDR copy
- Indicates the reports are in English l
ENCLOSURE G f
l 1
OFFICE OF STATE PROGRM S ITDS OF INIEREST WEEX Et0ItC JNUARY 22, 1982 l
i i
Robert Wood testified aa January 19, 1982 before the. California Public Utilities Ccranission en the IRC staff's views on assuring funds for l
deccrnissioning nuclear pcrer plants.
8 A two week Urmih Mill Licensing.and Inspection Training. Course for..
Agreemnt. States will be given starting January 25,.1982 at IEC Headquarters.
Representatives of RSS, IE, RES, IGR and SP will participate in the course.
On January.22, 1982 John Collins, Regional Ad:ninistrator, Region IV; Clyde Wisner, Public Information Officer, Region IV and Jim Fbntgomery, Regional State 1.iaison Officer, Region IV were in Denver reeting with Colorado State officials. Topics for discussion included Region IV's changing roles under regionalization plans, the recent. Fort Vrain em rgency response appraisal and the Rocky Fbuntain Im level Radioactive Waste Compact.
I 1
I ENCLOSURE H l
l I
{
i
i 0FFICE FOR ANALYSIS AND EVALUATION l
OF OPERATIONAL DATA ITEM OF INTEREST i
[EEK ENDING JANUARY 22, 1982 Case Study on BWR Vessel Level Instrumentation Following completion of the peer review, AEOD has completed a case study on vessel level instrumentation in boiling water reactors (BWRs). The study was initiated following events at Brunswick 1 on January 20, 1981 and Browns Ferry 2 on March 13, 1981.
The study included the review of a number of operating reactor events involving BWR vessel level instrumentation. The review has shown several cases where interaction between plant control systems and protection systems are evident.
Our evaluation of.hese cases has raised the safety concern of a single random failure in the vessel level instrumentation system causing a control system action that could (1) result in a station condition requiring protective action and, at the same time, (2) prevent proper action of some of the
+
protection system channels designed to protect against such a condition, leaving the remaining protection system channels to provide the protective function. A further single active failure in the remaining channels could then prevent the required protective actions.
The study addresses the interaction between feedwater control, reactor protection, containment isolation and emergency core cooling systems and includes findings and recommendations regarding these systems and the safety con cern.
Although the postulated control system or protection system interaction was not considered an immediate concern, AEOD believes that the safety concern and associated problems needs to be addressed. Thus, the report was forwarded to NRR for appropriate action.
1 i
I I
ENCLOSURE K i
f
~
UNITED STATES
' NUCLEAR REGULATORY COMMISSION WAsHlNGTON, D. C. 20555
' ' ' " ^ " ' ' ' '
INFORMATION REPORT "" '-82-so For:
The Comissioners From:
T. A. Rehm, Assistant for Operations, Office of the EDO Subjecti WEEKLY INFORMATION REPORT - WEEK ENDING JANUARY 29, 1982 1
A surnary of key events is includtd as a convenience to those Comissioners i
who may prefer a condensed version cf this report.
P Contents Enclosure Administration A
l Nuclear Reactor Regulation B
Nuclear Material Safety and Safeguards C
l Inspection and Enforcement D
Nuclear Regulatory Research E
Executive Legal Director F
l 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*
i Regions M
Items Approved by the Commission DISTRIBUTION: Co:=nissioners Commission Staff Offi s
=
~
EDO' T. A. Re.
stant for Operations ACRS Office of the Executive Director r Operadons
- No input this wrek.
Contact:
A. Rehm, CEDO FOR INTER.AL NR:
4 -2775I DISTRIBUTION ONLY, q u c \\c;u u x -
i 4eo2/ 6 c3 go l
N d' bO I
~
~J D
SUMMARY
OF WEEKLY INFORMATION REPORT Week Ending January 29, 1982 TMI-l Steam Generator Problem GPU and NRC staff met to discuss the steam generator problem. The problem appears to be caused by intergranular attack from the primary side resulting in the development of very tight circumferential cracks. The licensee is conducting a comprehensive program in the areas of eddy current testing, tube failure analysis, accident analysis and tube repair techniques, which will take about six months to resolve.
Removal of TMI Prefilter EPICOR II Liners DOE, through the July 1981 memorandum of understanding with NRC, has agreed to accept the 49 prefilter EPICOR 11 liners (that have been stored in the onsite solid waste storage facility) for R&D purposes and for final disposition. The licensee's current program for shipping the prefilters includes steps for inerting, sampling and integrity inspection. A special inerting tool will purge the excess hydrogen gas and inert the liner with a nitrogen cover gas.
The first inerting is tentatively scheduled to begin in late April 1982, with shipments beginning in early May 1982.
10 CFR Part 61 The coment period on 10 CFR 61, " Licensing Requirements for Land Disposal of Radioactive Waste," and the Draft Environmental Impact Statement on Part 61 closed as of January 14, 1982. Over one hundred comments are now being reviewed.
Washincton State A Bill was introduced in the Washington State Legislature proposing to reduce the volume of low level nuclear waste accepted by the State's storage facilities.
f
OFFICE OF ADMINISTRATION Week Ending January 29, 1982 ADMINISTRATION OF THE FREEDOM OF INFORMATION ACT STATUS OF REOUESTS Initial Appeal of Recuest Initial Decision Received 79 4
Granted 23 0
Denied 5
3 Pending 51 1
ACTIONS THIS WEEK Received C. D. Henry, III, Requests a copy of the non-proprietary portions of ETA Engineerino, Inc.
the winning proposal from Science Applications, (82-19)
Inc. that led to Contract No. NRC-80-02-035.
Thomas C. Wheeler, Requests five categories of documents regarding Pettit & Martin Atlas Machine & Iron Works, Inc. of Gainesville, (82-20)
Jim Thomas, Requests information on bargaining unit positions NTEU President which were filled by selections from outside of (82-21 )
the bargaining unit during the period from August 1 1981 and December 31, 1981.
William E. Todd, Requests a computer tape containing information Seimens Gammasonics, Inc.
on all NRC licensees.
(82-22)
Harold J. Spelman, Requests a copy of a letter from the NRC to Harold J. Spelman Kerr-McGee Chemical Corporation requesting Kerr-and Associates McGee to submit a plan for decontamination of (82-23)
Kress Creek near West Chicago, Illinois Kerr-McGee facility.
Harold J. Spelman, Requests the classification of Kerr-ficGee Chemical j
Harold J. Spelman Corporation facility in West Chicago, Illinois and Associates as an " Option V" site under the NRC's Branch (82-24)
Technical Position on " disposal or on-site storage of residual thorium or uranium from past operations CO*: TACT:
J. M. Felton l
492-7211 ENCLOSURE A f
I 1
2 Received, Cont'd (An individual requesting Requests information in the NRC on himself.
information about himself)
(82-25) i i
Steven C. Shelly, Requests a copy of a memorandum from Harold R.
Denton to NRR Division Directors dated 7/10/81 Union of Concerned directing that no resources be expended on Scientists NUREG-0660 Priority 2 and 3 issues until FY 83.
(82-26)
(Individuals requesting Request" information on their Licensed Operator information about themselves)
Examination results.
(82-27 thru 82-50)
David S. Fleischaker Requests four categories of documents regarding (8 2-51 )
the investigation of the false information conveyed i
by representatives of Pacific Gas and Electric Company to the NRC staff during a November 3,1981 meeting on the Diablo Canyon Nuclear Power Plant design reverification program.
1 Granted Susan E. Shearer, In response to a request for four categories of Abrams, Kovacs, Westermeier documents which pertain to the computer security J
& Goldberg, P.C.
requirements in OMS Circular A-71, made available (E1-409) 19 documents.
Tanya K. Konjolka, In response to a request for all documents relating tturphy, Lamere, to the investigation of a named person's over-and Murphy exposure to radiation which occurred on November 23 (El-509) 1977 at the Pilgrim Nuclear Power Station, made available 49 documents.
Kathleen H. Shea, In response to a request for seven catecories of Lowenstein, Newman, documents relating to John C. Haynes & Co.,
Reis & Axelrad Heath, Ohio, made available seven documents.
(81-512)
Malcolm H. Philips. Jr.,
In response to a request for four categories of Debevoise & Liberman records regarding the agreement between NRC and (82-7)
IEEE regarding accreditation of testing organizations, made available seven documents.
Informed the requester two additional documents are already available at the PDR.
ENCLb5'URE'A i
3 Granted, Cont'd Malcolm H. Philips, Jr.,
In response to a request for seven categories of Debevoise & Libeman records regarding the proposed rule on (82-8)
Environmental Qualification of Electric Equipment for Nuclear Power Plants, made available two documents.
Don Hoffman, In response to a request for documents pertaining The Clarion-Ledger to the sale or proposed sale of Tennessee Valley (82-9)
Authority (TVA) excess power capacity to any and all utilities and other distribution systems outside the service area of the TVA, made available selected pages from the latest official submission from TVA, the Bellefonte Operating License -
Environmental Report that discusses outside sales and purchases.
Scott Schulke In response to a request for a listing of ali NRC (82-12) licensed, U.S. located, non-commercial nuclear reactors, and a listing, by location, of all NRC licensed, low and high level. radioactive waste storage sites, made available three documents.
Informed the requester there are no licensed high level radioactive waste sites.
Stephen A. Wachter In response to a request for information between (G2-14)
General Public Utilities /lietropolitan Edison and the NRC regarding the Three Mile Island Unit 1 (TMI-1) restart program, informed the requester that documents pertaining to the restart of TMI-l are available at the Local Public Document Room in Harrisburg, Pennsylvania.
Joan A. Estrada, In response to a request for copies of invoices Professional Carpet for all carpet installation, repairs and soil Service extraction for November and December 1980 and (82-15)
December 1981, informed the requester the NRC has no invoices for the months listed in her request. However, we made available portions of two purchase orders that cover the period from October 1981 to July 1982.
ENCLOSURE A r 1
i l-i 4
(
l f,
i Denied Robert W. Frantz, In response to a request for four categories of Hamel, Park, documents regarding Technical Criteria contained McCabe & Saunders in Appendix A to 10 CFR Part 40, made available i
(81-328) over 700 documents. Denied one document in its entirety containing information submitted and l
received in confidence from a foreign source.
l Denied two documents in their entirety containing j
advice, opinions and recomendations.
j Robert F. Schiff, In response to a request for records relating to Washington Service a license held by New York Shipbuilding Corporation j
Bureau, Inc.
of New Jersey, made available 70 documents. Denied j
~
(81-468) portions of 17 documents, the disclosure of which l
would constitute a clearly unwarranted invar'on 4;
of personal privacy.
i (NRC employee)
In response to a request for information pertaining j
(82-1) to Vacancy Announcement No. 81-5636,' denied pn-tior:
of the Candidate Evaluation, Certificatior. and 8
1 Selection Record (CERT), disclosure of wh'Th would I
constitute a clearly unwarranted invasio, c f personal privacy.
i j
Douglas Lowenstein, In response to an appeal to the Commission and Cox Newspapers to the EDO regarding documents relating to the 1
(81 - A-15-81 -376 )
report of the NRC Office of Inspector and Auditor 4
(OIA) regarding the adequacy of the Office of j
Inspection and Enforcement (I&E) investigation
{
into quality assurance / quality control problems at the William H. Zimer Nuclear Power Station, the Comission denied two transcripts in their entirety, the discussions of which focused on the review of investigatory reports and the consideration of potential enforcement actions, including the imposition of civil penalties, all within the context of an ongoing agency adjudication. Also denied four documents in j
their entirety containing advice, opinions anr1 i
recommendations regarding the Comission resolution of the Zimer matter. The EDO made available 14 j
documents and denied portions of two documents, i
the release of which would constitute an unwarranted invasion of personal privacy and disclose the identities of confidential sources.
I
.1 I
I i
ENCLOSURE $
i i
I 1
i ~
I l
5 t
i l-l Denied, Cont'd Lee L. Bishop, In response to an appeal to the Commission of Harmon & Weiss the denial of access to documents relating to (81 - A-18-81 -397 )
the Commission's decision to reconsider its l
military functions exception to NRC rules of l
procedure,10 CFR 2.700a, the Commission continued to deny the five documents in their entirety 1
containing predecisional advice, opinions and recommendations.
l 1
i i
l 1
)
i l
ENCLOSURE,A I
+
DIVISION OF CONTRACTS l
Week of January 29, 1982 CONTRACT AWARDED i
l 1.
RS-NMS-82-031 Title
" Assessment of Waste Retrieval Alternatives" Description - Identify and evaluate alternatives being considered hy DOE for retrievability or recoverability of high level waste from geologic repositories as defined in existing conceptual designs.
Period of Performance - Two Years Sponsor - NMSS Status - A Cost Plus Fixed Fee Contract in the amount of $350,804.00 was awarded to Engineers International, Inc. of Downers Grove, IL.
effective January 26, 1982.
CONTRACTS CLOSED OUT
( All administrative action comoleted and final Dayment nede)
(
CONTRACT NO.
CONTRACTOR CLOSE-0UT-DATE f
NRC-10-80-675 Paul E. Weil 1-25-82 tiRC-05-77-06:
Teknekron Research, Inc.
1-29-82 l
'4RC-04-77-126 f1IT l-29-82 l
ENCLOSURE A l
HER WEEKLY HIGHLIGHTS Week Ending January 29, 1982 1
AND-2 SEISMIC ACTIVITY There has been news media interest in seismic activities which occurred on 1/20/82 about 60 miles east / north east of the AND plants. The disturbances occurred about 6:00 PM, measured 4.5 on the Richter Scale and were not generally noticed in the plant site area.
The seismic monitoring equipment at ANO, which is set t'o record above 0.01 g, was not activated. Operability of the equipment was confirmed by plant staff after the event. The site SSE and OBE values are 0.20 g and 0.10 g.
TMI-i STEAM GE"ERATOR PROBLEM ine Scaff cet with GPU January 25th to get an update on the steam generator problem at Till-1. The techanism appears to be intergranular attack from the primary side resultine in the development of very tight circunferential cracks.
Virtually al1 defects are located in the upper tube sheet. area near the roll
~
transition area of the tube. There is evidence of sulphur and chlorine impurities in every defect on the two removed tubes which have been extensively
~
examined to date.
Sulphur is presently the suspect impurity.
The licensee is ccnducting a comprehensive program in the areas of eddy current l
testing, tuhe f ailure analysis, accident analysis and tube repair techniques.
He presently estimates that it will take about six months to resolve this Fernaps the ecst important efforts now underway relate to metallogriphy prcblem.
These efforts should confirm the ano cnemical analysis of 19 removed tubes.
type cf terrosion, identify the causative agent and the rate of crack growth.
Tr.e present prc;csed nethod for interim solution of this problem is to plug
~
Since block plugging of many tubes defective tubes with removable plugs.
l (several thousand) can crecte undesirable thermal hydraulic effects on the I
iscendary side and affect other accident analyses, the licensee is planning l
cn derating some.; hat to' compensate.
Ecth the licen:ee and the staff have set up task forces and are employing.
eve v recc:nized consultant in these areas. The staff and its, vi rtually consulta'nts will independently review eddy current data, operational che:1str.-
data, susceptibility of other prittry systen r.aterials and results of thernal
~
Additionally staff censultants will be visiting Battelle h<draulic analyses.
l and E2' (labs used by GPU) to review methods and results of tube examinations.
l ENCLOSURE B 1
f
SAN C"D~:.E UNIT 2 15, 1982, the California Coistal Comission voted'B-4 to On friday, January defer action for 30 days on Southern California Edison's (SCE) application for
(
an amendment to the Coastal Comission permit for San Onofre 2 and 3 which t
was issued in 1974. The preposed amendment involves restrictions on use of the beach within the exclusion area, and is acceptable to the Coastal Comission j
staff, according to SCE.
1 Meetina Notice
Subject:
Clinch River Breeder Reactor Structural Review Meeting i
i Date/ Time:
February 17,1982 at 8:30 a.m.
Location:
Air Rights Building, Room 2242, Bethesda, Md.
Attendees:
J. Longenecker, D. Goeser, et. al. (DOE)
C. P. Tan, R. Stark, et. al. (NRC l
I
\\
e ENCLOSURE B t
\\.
NRC THI PROGRAM OFFICE WEEKLY STATUS REPORT l
January 24, 1982 - January 30, 1982 l
l Plant Status _
l Core Cooling Mode: Heat transfer from the reactor coolant system (RCS) loops to reactor building ambient.
l I
Available Core Cooling Modes: Decay heat removal systems.
Long tem 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.
I Major Parameters (as of 0600, January 29,1982) (approximate values)
Average Incore Themocouples: 106*F Maximum Incore Thermocouple:
136*F RCS Loop Temperatures :
A B
Hot Leg 97'F 100*F-Cold Leg (1) 77'F 80*F (2) 80*F 84*F RCS Pressure: 96 psig Reactor Building: Temperature :
61 *F Water level :
Elevation 285.2 ft. (2.7 ft. from floor)
Pressure :
-0.15 psig Airborne Radionuclide Concentrations:
<5. 0 x 10-6 Kr85
<5.7 x 10-9 H3 (samples taken 1/28/82)
Effluent and Environmental (Radiological) Infomation 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 January 22, 1982, through January 28,1982, the effluents contained no detectable radioactivity at the discharge point although individual effluent sources which originated within Unit 2 contained minute amounts of radioactivity. Calculations indicate that less than one millionth (0.000001) of a curie of cesium was discharged.
1 ENCLDSURE B i
. i l
2.
Environmental Protection Acency (EPA) Environmental Data.
Results from EPA monitoring of the environment around the 5n sTte were as follows :
3 The EPA measured Kr-85 concentrations (pCi/m ) at several environmental monitoring stations and reported the following resul ts :,,
loca tion December 28. 1981 - January ll,1982 (pCi/m3) 29 Gol dsboro Observation Center 22 27 Middletown 22 Yorkhaven All of the above levels of Kr-85 are considered to be background level s.
No radiation above normally occurring background levels vas detected in any of the samples collected from the EPA's air and gamma rate networks during the period from January 20,.1982, through January 28, 1982.
j 3.
NRC Environmental Data.
Results from NRC monitoring of the environment around the IM1 site were as follows:
The following are the NRC air sample analytical results for the onsite continuous air sampler:
1-1 31 Cs-137 Samole Perio d_
(uCi/cc)
(uCi/cc)
HP-304 January 20, 1982 - January 2B_,1982
<5.4 E-14 <5.4 E-14 4.
Licensee Radioactive Material and Radwaste Shipments.
On Tuesday, January 26, 1982, one drum containing two,1-foot sections of Unit 1 steam generator tubes was shipped to Battelle-Columbus Laboratory, Columbus, Ohio.
On Wednesday, January 27, 1982, 34 one liter Unit 1 samples, l
taken from various tanks and locations, e.g. core flood tanks, l
bleed tanks, reactor building spray pumps, etc., were shipped in 14.: containers to Babcock and Wilcox (B&W), Lynchburg, Virginia.
On Wednesday, January 27, 1982, one drum containing four,1-foot l
sections of Unit i steam generator tubes was shipped to Babcock and Wilcox (B&W), Lynchburg, Virginia.
I ENCLOSURE B
i i
i
. i f
f On Wednesday, January 27, 1982, seven drums and one LSA container (box), containing steam generator inspection and repair equipment, were returned to Babcock and Wilcox (B&W), Lynchburg, Virginia.
4 i
Major Activities j
1.
Submerged Demineralizer System (SDS). Processing of batch 17 was i
completed on January 29, 1982. On January 30, 1982, the transfer of batch 18 from the reactor building sump was commenced. SDS performance 4
parameters for batch 17 are included in Attachment 1.
1 The radioactivity in the spent fuel pool water is now approximately 1
6 x 10-3 uc/ml (gross B-y activity). The supplemental spent fuel
'j pool cleanup system is expected to become operational during the next report period.
2.
EPICOR II__.
The EPICOR 11 system continued to process SDS effluent during the week.
Performance parameters are enclosed.
.i l
3.
Reactor Building Entries.
One of two scheduled reactor building (RB) entries was completed during the last week in January. Tasks perfomed during the completed entry included video taping of a,reas 1
in the PS and additional testing of neutron source range monitor, NI-2.
The scheduled load test of the crane mounted supports for the power lift was not perfomed. The second of the two scheduled entries was cancelled after the RB purge was secured due to problems in the purge train electrical power supply.
The electrical problems in the RB purge system have been repaired and RB entries are scheduled to resume during the first week in February.
In addition to load testing, the power lift supports during l
the entries next week, the power lift will be assembled in the RB and j
work will commence to ensure that fire fighting stations inside the j
A site NRC Radiation Specialist with the TMI Program Office will participate in the next reactor building entry.
The inspector will perform independent radiological measurements to verify the licensee's information.
Also, an independent verification of general conditions in the RB will be made. The licensee performance a
and compliance with radiological safety requirements will be verified under actual working conditions in the RB.
4.
EPICOR 11 prefilter Status.
Forty-nine first stage prefilter (PF)
EPICOR 11 liners are currently stored in the onsite solid waste storage facility. These 4' x 4' PF liners were generated during a
the processing of auxiliary building water (approximately 500,000 gallons) after the March 28, 1979 accident.
Typically these liners contain 40 ft3 of ion exchange media with radioactivity loadings from 200 to 1,300 curies predominately as cesium-137.
ENCLOSdREB '
o
i
. DOE, through the July 1981 memorandum of understanding with NRC, has agreed to accept these 49 EPICOR II PF for R&D purposes and for l
final disposition.
One of the higher activity liners (PF-16) was l
shipped by DOE to Battelle Columbus Laboratories on May 19, 1981, j
for detailed analysis.
These analysis indicated no significant i
degradation of liner integrity nor ion exchange media. Measurable amounts of hydr. ogen gas generation in the prefilter were confirmed; however, oxygen which is necessary for a combustible mixture, was also confirmed to be depleted to a level to preclude any internal 1
combustion or explosion. Because of the hydrogen inventory, GPU has
(
instituted procedural controls and monitoring to assure no flammable condition nor ignition sources exist at the storage module area, i
The licensee's current program for shipping these 49 prefilters includes steps for inerting, sampling and integrity inspection. A special inerting tool has been developed and tested at the Idaho l
National Laboratory for use by GPU. This tool, which is scheduled for shipment to TMI in early February, will both purge the excess j
hydrogen gas and inert the liner with a nitrogen cover gas. After inerting and leak testing, the liners will be shipped individually j
to the Idaho National Laboratory in standard type "B" shipping casks which are designed to withstand transportation accidents.
i GPU is currently developing support hardware and procedures for the' l
inerting and handling evolutions. The first EPICOR 11 prefilter (PF-2) inerting is tentatively scheduled to begin in late April 1982.
Shipments should begin in early May 1982.
ENCLOSURE.B.
1 l
l
- - ~
Meetings Held 1.
The NRC's Advisory Panel for the Decontamination of TMI Unit 2 met on January 28, 1982, in Harrisburg.
Status reports were given by GPU, NRC, EPA, 00E, and comments were offered by several members of the publ i c.
EPA representatives stated that their Agency was not reducing operations at JMI despite nationwide reductions in many of EPA's Dauphin County Commissioner Larry Hachendoner supported programs.
decoupling the Unit 1 startup from the Unit 2 cleanup by applying the Deferred Energy Surcharge which is due to expire in June 1982, toward the cleanup.
No date has been set for a future meeting.
2.
On Friday, January 29, 1932, Lake Barrett met with a group of area mothers to discuss various TMI issues, including the status of Unit 1 steam generator tube conditions, the forthcoming decontamination experiment, and the financial problems.
Future Meetings 1.
On Friday, February 26, 1982, Lake Barrett will be speaking for the dinner meeting being held by the Engineers Week Joint Planning 4
Council to honor Lehigh Valley's Engineer of the Year and Young-
)
Engineer of the Year.
2.
On Saturday, March 13, 1982, Lake Barrett will address the Society i
of Manufacturing Engineers in Williamsport, PA, on the cleanup of TMI and general aspects of nuclear power.
ENCLOSURE B i
1 1
r i
j
~
t i
l ATTACHMENT I SDS Performance for Batch Number 17 Average Average Average Radionuclide_
Infl uent Ef fluent OF (ut/ml)
(uc/ml) 5 Cesium 137 94 9.1 x 10 4
- 1. x 10 2
Strontium 90 3.0 7.6 x 10-3 4.0.x 10 EPICOR II Performance January 11,1982 to January 28, 1982 Average Average Avera ge Radionuclide I n fl ue n_t_
Ef fl uent_
DF (uc/ml)
(uc/ml) 3 i
Cesium 137 9.6 x 10-4
<2.6 x _10-7__
> 3_. 4, _x _1,0 Strontium 90 6.2 x 10-3 4.8 x 10-6 1.3 x 103 4
Antimony 125 1.1 x 10-2
<4.1 x 10-7
>2.5 x 10 ENCLOSURE B,'
I l l
4
0FFICE OF NUCLEAR MATERI AL SAFETY l'? SAFEGUARDS.
Items of Interest i
Week Ending January 29, 1982 Visit by General Electric Representatives GE representatives will visit the NRC on February 1 and 2,1982. While here, they wish to hold informal discussions concerning a draft of their revised physical security plan for the Morris Illinois Spent Fuel Storage Facility as well as future safeguards requirements for spent fuel shipments and storage.
Comment Period on 10 CFR Part 61 Closed The comment period on 10 CFR 61, " Licensing Requirements for Land Disposal of Radioactive Waste", and the Draft Environmental Impact Statement (DEIS) on Part 61 closed as of January 14, 1982. Over one hundred comments from individuals and organizations have been received. The comments are now being reviewed.
United Nuclear Corporation (UNC)
At the request of United Nuclear Corporation, the NRC staff met with Messrs. Emeigh, Gregg, and Spurgeon on January 26, 1982, to discuss UNC's schedule for decommissioning the Wood River Junction site. At present, UNC is decontamina-ting the remaining facilities on the site. Soil decontamination is scheduled to commence in May of 1982. Complete decontamination is scheduled to be finished by mid-December 1982. Shipment of the waste for disposal is now scheduled to start in mid-June 1982, to be completed the first of May 1983. A final UNC survey and re-i quest for termination of the license is anticipated by mid-May 1983. NRC's schedule for verification surveys has not been decided, but should follow either the decontamination schedule for UNC or immediately after receipt of the final survey and request for termination of the license. The NRC. schedule will be better defined as the UNC decontamination effort progresses.
1 ENCLOSURE C t
i i
l-t Planned Meetings - Division of Safecuards
Subject:
Action Plan Working Group Meeting Date:
February 2, 1982
. Location:
Department of Sate Attendees:
Kenneth Sanders, NMSS
. Represent,atives of IP, State, DOE, ACDA
Subject:
Initial 73.55 Plan Review and Site Visit Date:
February 2 - 5, 1982 l
Location:
Perry Nuclear Station Attendees:
D. Kunze Representative from Region III Licensee
Subject:
Mtg w/ Dr. Alexander Robnagel, Germany, to discuss threat of l
nuclear terrorism Date:
February 4, 1982 Location:
R. F. Burnett's Office Attendees:
R. F. Burnett, G. W. McCorkle Absences of Director end Deouty Director N0NE
~
i l
l l
ENCLOSURE C f
j Meetines - Division of Fuel Cycle and Material Safety
- 1. '
Subject:
To dis ~ cuss' amendment for' a new prociss line and production of for the conversion of UF6 007 pellets.
Date/ Time:
Fe5ruary.2
'8:00-4:00-i Location:
Willste Building - 8th floor conference room
[
Attendees:
G..Bidinger (FC), Representatives from i
Westinghouse 2.
Subject:
Sequoyah Plant - Kerr-McGee proposed disposition of radium bearing residues.
Date/ Time:
February 2 - 1:30 i
Willste Building - 5th floor conference room Location:
W. T. Crow (FC), W. A. Nixon (FC), R. G. Page (FC),
Attendees:
R. H. Odegaarden (FC), D Nussbaumer (SP),
Representative from Kerr-McGee 3.
Subject:
Development of Accident Analysis Handbook (Fuel Cycle Facility Safety Research Program Date/ Time:
February 3 - 4 Location:
Seattle, Washington Attendees:
J. E. Ayer (FC), P. Loysen (FC), S. Bernstein (RES),
Representatives from Pacific Northwest Laboratory, l
l Representative from Los Alares National Laboratory 4.
Subject:
To participate in the workshop of the New York Academy of Medicine to discuss low-level institutional waste.
Date/ Time:
February 8 - 9
)
Location:
New York 1
Attendees:
Lidia A. Roche (FC)
ABSENCES OF DIRECTOR OR DEPUTY DIRECTOR None u
e ENCLOSURE.C.
f f
....,_..,,_,_m
l=
l l
t Meetines - Division of Waste Manacement l
1.
Subject:
Discussi m of 10 CFR Part 61 Date/ Time:
February 1,1982
' Location:
Room 736, Willste Building R.' Dale Smith, Paul H. Lohaus, Timothy Johnson, and Attendees:
Gary Roles, WMLL; John Stewart, Werner, Pfleiderer Corp.
2.
Subject:
DOE /NRC Meeting on High-Level Waste Pre-Licensing Issues l
Date/ Time:
February 3,1982 3
Location:
Willste Building l
Hub J. Miller, John Greeves, Phil Justus, kHHT; Michael J.
Attendees :
Bell, WMHL; Wade Ballard and Ralph Stein, DOE' 3.
Subject :
Discussion of the New kHUR Staff Technical Position on Hydrologic Design Criteria and its Impact on Riprap Requirements for Moab, Washington; Impacts on Surety i
Requirements for the Moab Mill l
Date/ Time:
February 3, 1982, 9:00 a.m.
Location:
Willste Buildina Attendees:
Ted Johnson, Harry Pettengill, Pete Garcia, kHUR; R. Blubaugh, R. Alcock, Atlas 4.
Subject:
Discussion of the Adequacy of Various Financial Income and Asset Tests as an Alternative Form.of Surety Covering Reclaration and Decommissioning Activities -
Date/ Time:
February 3,1982 Location:
Denver, Colorado Attendees:
Kathleen Hamill, WMUR; R. Fonner, ELD; Colorado Department of Health; Colorado Attorney General's Office; various industry. representatives 5.
Subject:
Meeting with Exxon Minerals and Silver King Mines to Discuss the Possible Sale of Exxon's Highland Uranium j
Mill to Silver King Mines and the Resulting Transfer of j
l Source Paterial License SUA-1139 i
I Date/ Time:
February 4, 1982, 9:00 a.m.
Location:
Willste Building Attendees:
Harry Pettengill, Pete Garcia, Samuel Jones, WMUR; Paul Estey and representatives from Exxon and Silver King 6.
Subj ect:
10 CFR Part 61 Waste Form and Classification Requirements Date/ Time:
February 8,1982 Location:
Augusta, GA - ASME Workshop on Radwaste Practices Attendees:
Timothy Johnson, kHLL; Tom Quaka, Chaiman (Comonwealth Edison) 7.
Subject:
Semi-Annual Contract Meeting with Golder Date/ Time:
February 9-10, 1982 Location:
Room 110, Willste Building Attendees:
C. L. Pittiglio, John Greeves, Lud Hartung, WMHT; Tim.Hagan, TACB; David Pentz, Golder ENCLOSURE C f.
i j
1.
l I
l
_2-8.
Subject:
Semi-Annual Management and Technical Review Heeting with Golder Date/ Time:
February 11, 1982 Location:
Room 110, Willste Building Attendees:
Lud Hartung, John Greeves, WMHT; Tim Hagan, TACB Richard Gates and David Pentz, G,lder Absences of the Director and Deputy Director i
NONE
[
I l
l 1
ENCLOSURE C
l i
1 i
0FFICE OF INSPECTION AND ENFORCEMENT I
ITEMS OF INTEREST January 25, 1982 to January 29, 1982 1
I 1.
There were no Significant ' Enforcement Actions imposed during the past week.
2.
Preliminary Notifications relating to the following actions were dispatched l
during the week:
a.
PNO-I-82-09, 09A, 09B, 09C R. E. Ginna Nuclear Power Plant -
l Steam Generator Tube Rupture; Site Emergency.
b.
PNO-I-82-10, Vermont Yankee Nuclear Power Corporation (Vermont Yankee) - Unscheduled Plant Shutdown.-
c.
PNO-I-82-11, Duquesne Light Company (Beaver. Valley Unit 1) - Assistant to Nuclear Division Vice-President Resigns.
d.
PNO-I-82-12, Duquesne Light Company (Beaver Valley Unit 1) - 4160 i
VAC Cable Failure and Partial Loss of Offsite. Power.
i e.
PNO-III-81-121A, Dairyland Power Cooperative (Lacrosse) - Plant Scram With Loss of Off-Site Power.
f.
PNO-III-82-08A, Illinois Power Company (Clinton Unit 1) - Firing of l
Electrical QC Inspectors.
g.
PNO-III-82-09B, Commonwealth Edison Company (Quad Cities Unit 2) -
Cracks in Reactor Water Cleanup System Inside Drywell, Update.
j h.
PHO-III-82-11, Consumers Power Company (Palisades) - Operational Problem Resulting in an Outage Which is Expected to Last Longer Than l
Two Days.
i l
1.
PNO-III-82-12, Commonwealth Edison Company (Zion Unit 2) - Outage Longer Than 48 Hours,
- j. PNO-III-82-13, Cocmonwealth Edison Company (Zion) - Videotaped Threats Against Zion Received By Chicago Area News Media.
3-Other Items:
l a.
Activities of the Division of'Emercency Precaredness 1.
January 28, 1982 EPLB Section Chief participated in the final exit meeting with the Jersey Central Power and Light (Oyster Creek) staff concerning the emergency preparedness findings resulting from the recent appraisal.
l ENCLOSlfRE D' l
l
i i
~
2-l i
- 11. January 29. 1982 A representative from DEP and Region I participated in a meeting l
at the TMI' site with FEMA, PEMA, NRC and Met Ed personnel to i
discuss the partial initial decision findings by the ASLB hearing l
panel concerning emergency preparedness issues.
i i
l b.
Activities of the Division of Reactor Procrams 1
Jim Taylor, Division Director, will attend an IEEE meeting.in New York City on Monday, February 1,1982 concerning laboratory accreditation.
On Wednesday, February 3,1982, Jim Taylor will meet with INP0 in Atlanta to discuss the development of a memorandum of understanding related j
to INP0 evaluations of operating plants.
l 1
c.
Activities of the Enforcecent Staff l
?
On Thursday, January 28, 1982, an enforcement conference was held between the corporate management of Boston Edison Company and IE i
staff to discuss the January 18, 1982 enforcement action.
l I
I l
l l
l l
l l
i j
ENCLOSURE D 1
~
1 0FFICE OF NUCLEAp, REGULATORY RESEARCH IMPORTANT EVENTS FOR THE WEEK ENDING JANUARY 29, 1982 l
I j
Experimental procrams Branch 1.
Data Bank i
Data from the Neptune Test Series (a new data source) were. entered into the data bank; 5000, 5001, 5002 and 5004. The data refers to the simulated reactor core boiloff experiments.
data (inpile data of pre and, post-CHF) were also PBF-PCM2 test added to the data bank.
i i
2.
Semiscale i
Further study of Test S-IB-1, the 100 percent cold leg break still A
shows no oscillatory behavior of the type observed in S-07-6.
repeat of S-07-6 was conducted on January 22, 1982 and no oscillatory l
behavior was observed. The present plan is to conduct 50 percent break and the 19 percent break during February 1982. The latter is a j
LOBI counterpart test and all conditions are being set as close as l
practical to those existing in a LOBI test which has been conducted.
l i
Fuel Eehavior Branch l.
PBF Procram The failure of the PBF coolant pump and the subsequent inoperable condition of its replacement may cause a delay of 1 month in the overall TFBP exper-1 mental program. It is certain that the OPTRAN 1-1 test schedule for early February will be impacted. OPTPAN 1-2 may be postponed until after the August severe fuel damage test SFD-1. Replacement parts are available l
for the inoperable pump, and pump vendor personnel have been contacted and will assist PBF personnel to get an operating pump back on line as soon as possible. More detailed information will be available next week.
Publications Issued Durine the Week of January 25-29, 1982 Response-Time Testing Draft Regulatory Guide and Value/ Impact Statement:
of Protection System Instrument Channels, Task IC 121-5, ' Comments requested by March 31, 1982.
Contact:
A. S. Hintze (443-5966)
ENCLO$URE E f
I 0FFICE OF THE EXECUTIVE LEGAL DIRECTOR ITEMS OF INTEREST WEEK ENDING JANUARY 29, 1982 St. Lucie Plant, Unit No. 2 On January 29, 1982, the Appeal Board issued a Decision (ALAB-665) in which it affirmed the Licensing Board's decision to deny a late petition to intervene in the construction permit antitrust review proceeding by Parsons and Whittemore, Inc.
l 1
i I
l ENCLOSURE F l
I
i ITEMS OF INTEREST 0FFICE OF INTERNATIONAL PROGRAMS WEEK ENDING JANUARY 29, 1982 NRC-CNEN Arrancement Renewed IP has been advised that U.S. Ambassador to Brazil Langhorne A. Motley and Brazilian National Nuclear Energy Commission (CNEN) President Hervasio G. de Carvalho signed the renewal " Arrangement Between NRC and the CNEN for the Exchange of Technical Information and Cooperation in Regulatory 'and Safety Research Matters" in Rio de Janeiro on January 14, 1982. The signing ceremony was followed by a question and answer period with Brazilian representatives. The staff awaits receipt of the signed arrangement copies.
l wnich are being pouched to State.
Visit by Mexican CNSNS Deleoation Four staff members from the Mexican National Nuclear Safety and Safeguards Commission (CNSNS) along with the I AEA Safety Advisor to Mexico visited various staff offices in IE and NRR from January 25-29 to discuss future i
technical cooperation activities. In addition, the delt7ation held meetings to gain more information on the subject of regulatory requ rements in the i
transition phase 'from construction to operation.
l j
l l
I
~
ENCLb5'URE'G l
l l
t i
I
- Foreicn Reports The following foreign reports were received in IP January 25-29:
j (For further information contact Eva Szent-Ivany, IP, X27788.)
From the FRG:
l KTA Safety Guides:
- 2201.2 Design for Nuclear Power Plants Against Seismic Effects.
Part 2: Site
- 2207 Flood Protection for Nuclear Power Plants
- 3205.1 Component Protection Construction with Non-Integral Connections for Reactor Coolant Components 3502 Accident Instrumentation
- 3602 Storage and Handlinr) of Fuel, Control Material and Neutron Sources in Nuclear Power Plants with Light Water Reactors I
3604 Storage, Handling and Inter-Operational Transport of Radioactive Materials (with the Exception of Fuel) in Nuclear Power Plants
- 3903 Crane Operation and Inspection in Nuclear Power Plants From Japan:
STA - Fast Breeder Monju Power Plant - Nuclear Reactor License Application i
c Trom S. Korea:
Monthly Operating Data for Ko-Ri Unit #1 - December,1981**
From Sweden:
SKI - Ringhals Unit 3 Plugging **
- Steam Generator Tube Plugging Margin Analysis for the Swedish State Power Board - Ringhals 3 Nuclear Power Plant **
- Ringhals 3 - Steam Generator Inspection Evaluation of Eddy Current Res ul ts **
- Summary of the Swedish Nuclear Power Inspectorate's Position on the Steam Generator Tube Frettings in the Ringhals 3 Plant **
Deleted from PDR copy
- Indicates the reports are in English ENCLOSl[ REG'
4
]
4 OFFICE OF STATE PROGRAMS-ITEMS OF INTEREST.
WEEK ENDING JANUARY 29, 1982
~
l Dr. Faith Brenneman, the.new Regional State Liaison Officer in Region I, was in Bethesda all week for orientation.
She met I
with the Commissioners, the EDO and key program office personnel.
]
i Senate. Bill (SB 4590) was introduced in the Washington State Legislature on January 19, 1982.
It proposes to reduce the volume of low level nuclear' waste accepted by.the Statets storage i
facilities.
The volume of. waste would be reduced over a three year period - the first year to 75%, the second to 65% and.the third year to 50% of the 1981 level.
The volume of waste accepted from States which are parties to the Northwest Interstate Compact on Low Level Radioactive Waste Management will be determined by l
l the Compact.
The 10-week. Health Physics course for State regulatory personnel, which is given by Oak Ridge Associated Universities, began on January 25, 1982.
l William B. Menezer, Regional State Lidison Officer, Region III.
was in Springfield, Illinois on January 26 meeting with Dan Illinois Commission.on Atomic Energy Williams, Executive Director,islation regarding radioactive waste to discuss proposed State leg l
l disposal.
Mr. Menczer also met with John Nordin, Supervisor of
)
the Bazardous Materials Unit of the Illinois. State Police, to i
discuss.10 CFR Parts 71 and 73 regarding advanced notification of j
spent fuel and waste shipments to Governors.
Illinois has its own.
law which requires spent fuel shippers in Illinois to. provide l
24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> advance notice to the Department of Nuclear Safety.
Part 73 regarding protection of safeguards information (schedule i
and itinerarv information) was discussed to insure that State notification' procedures provide for protection of the information.
The Director of State ProgrEms and the RSLO, Region IV, met.with the Director of the New Mexico Environmental Improvement Division on January 27 to discuss plans and schedules for negotiating an amended agreement with New Mexico pursuant to the Uranium Mill i
Tailings Radiation Control Act NRC has co=mented on the draft (December 22, 1981) Central Inter-sta e Low Level Radioactive Waste. Compact.
The' eligible States.
4 to this compact are Arkansas, Iowa, Kansas, Louisiana, Minnesota, i
l l
Miscouri, Nebraska, North Dakota and Oklahoma.
Areas of concern were identified and the NRC staff offered proposed resolutions l
to these concerns.
ENCLOSURE H' f
t k
The "Information Report on State Legislation" hEs stErted its subscription program, effective January, 1982.
All persons who are.not local, State or Federal employees must now pay an annual fee of $13.00 to receive the Report.
i 9
I i
l i
l 4
t
~
ENCLOSURE H l
i f
[
l
OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS Items of Interest k'EEK ENDING JANUARY 29, 1982 i
Power Plcnt 5.nedules Provided, through EDO, a response to Chairman Palladino's request for information on the contention that schedules can be decreased to about 5-1/2 years through design standardization.
Publications (1) Topical Report Review Status dated January 1982 NUREG-0390, and (2) Systematic Evaluation Program, NUREG-0485, dated December 1981, were distributed.
L l
i ENCLOSURE I i
i OFFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA j
ITEM OF INTEREST WEEK ENDING JANUARY 29, 1982 AEOD has compiled data on medical misadministrations reported by NRC licensees.
The misadministrations occurred between November 10, 1980 (the effective date i
for the misadministration reporting rule) and September 30, 1981. For this period AEOD had received copies of 300 reports from 216 licensees, who reported misadministrations involving 360 patients. Eight of the reported misadministrations involved therapeutic misadministrations; the remaining 292 reports concerned diagnostic misadministrations. About 70% of the diagnostic misadministrations involved administration of the wrong radiopharamaceutical, and about 25% were administrations of a radiopharamaceutical to the wrong patient.
Based on the number of reports received and a total of six to nine million nuclear medicine studies performed annually by NRC licensees, we estimate the error rate for nuclear medicine studies to be about 0.01%. To date, about 10%
of NRC licensees have reported one or more misadministrations.
r l
1 ENCLOSdREK' f
I
REGION V Items of Interest j
Week Endino January 29, 1982 i
y l
i l
Subagreement with State of Washington
)
l On January 19, 1982, a subagreement between the State of Washington and the NRC l
Region V office received the final signatures. The subagreement will allow the l
l NRC to take enforcement action against NRC licensees, utilizing infomation gathered by State of Washington inspectors. The subagreement applies only to i
shipments of radioactive waste from NRC licensees that are received at the Richland, Washington waste disposal site. The State of Washington maintains continuous inspector coverage at that location.
I I
I Portland General Electric Conpany Trojan - DN 50-344 As a result of fuel failures, the primary coolant dose equivalent iodine activity has been increasing for several months, reaching 60-65% of the Technical Specification limit a week ago.
Further, a gradually increasing l
primary-to-secondary steam generator leakage of 10-15 gallons per day (Technical Specification limit 500 gallons per day) was observed during the i
same time period. The licensee has no plans to shut down prior to the refueling outage scheduled for May 1982. The increased primary system activity level could result in significantly increased releases in the event i
of a steam generator tube failure.
i Meetina Notice 1
l
Subject:
NRC Regional Evaluation of Licensee Performance for the period June 1, 1980 through June 30, 1981, for Rancho Seco.
l Date/ Time:
February 25, 1932 at 10:00 a.m.
Location:
Sacramento Municipal Utility District' Headquarters, Sacramento, California Attendees:
R. H. Engelken, J. L. Crews, et. al. (RV); T. L. Hhrpster (IE);
M. L. Padovan and J. L. Stolz (NRR); W. C. Walbridge, et. al.
(Sacramento Municipal Utility District) 4 ENCLOSURE M i
t
+
ITEMS APPROVED BY THE COMMISSION - WEEK ENDING JANUARY 29, 1982 A.
STAFF REQUIREMENTS - AFFIRMATION SESSION 82-2, 3:50 P.M., THURSDAY, JANUARY 21, 1982 COMMISSIONERS' CONFERENCE ROOM, DC OFFICE (OPEN TO PUBLIC ATTENDANCE), Memo SECY to Dircks, Bickwit and Kammerer,1/26/82.
I.
SECY-81-679 - Amendment to 10 CFR Part 119: Export of I AEA Safeauarcs Samoles The Commission, by a vote of 4-11 (Commissioner Gilinsky disapproving),
approved for publication in the Federal Recister a final rule amending 10 CFR Part 110 to exempt IAEA safeguards samples from export license criteria, in accordance with Sections 57d and 54c of the Atomic Energy Act.
The Commission determined that the criteria in Section 127 of the Atomic Energy Act are met by the excmption.
In addition, the Commission requested that staff provide an ennual report which contains information regarding types and quantities of material exported to the IAEA in accordance with the US/IAEA Safeguards Agreemen t.
Commissioner Gilinsky supported the request for an annual report.
(IP) (SECY SUSPENSE:
2/8/82)
The Commissicn requested that:
1.
staf f provide a copy of the Federal Register Notice to affected licensees; and (ADt1/IP) (SECY SUSPENSE: 2/15/82) 2.
the apprcpriate Congressional Committees be informed.
(OCA/IP) (SECY SUSPENSE: 2/8/82)
\\
l I Sectien 201 of the Energy Reorganization Act. 42 U.S.C. !5841, provides that action of the Commission shall be determined by a
" majority vote of the members present." Commissioner Roberts was not present when this item was affirmed, but had previously indicated his approval of the item.
Had Commissioner Roberts been present, he would have affirmed his prior vote.
Accordingly, the formal vete of the Commission was 3-1 in favor of the decision.
i 1
ENCLOSURE N
\\
ITEMS "o"RCVED BY THE COMMISSION - WEEK ENDING JANUARY 29, 1982 A.
StaffRecuirements(cont'd)
II.
SECY-81-695 - Reconsideration of 10 CFR 2.700a (Exceotion from Procedural Rules for Adjudications Involvino Conduct of Military or Foreign Aff airs f unctions) and Acolication to Pending Proceedings The Comission, by a vote of 3-22 (Commissioners Gilinsky and Bradford disapproving), approved for publication in the Federal Recister a final rule to readopt that portion of 10 CFR 2 wnich provices an exception from those rules for adjudications involving the conduct of military or foreign affairs functions. The rule indicates that it may be applied to pending proceedings.
Commissioners Gilinsky and Bradford have provided separate views and Commissioner Ahearne has provided additional views, all of which will be published with the FRN.
(OGC) (Subsequently, on January 26, 1982 the FRN was signed by the Secretary).
III. SECY-81-703 - Comission Response to FOI A Aopeal (81-A-15C)
Regarding Transcriots of Zimmer Meetings 3
The Comission unanimously approved-a letter denying an appeal of the withholding of a meeting transcript and five other documents relating to Commission deliberations on the Zimer quality assurance controversy.
(0GC) (Subsequently, on January 22, 1982 the letter was signed by the Secretary).
I V.
SECY-82 FOI A Aopeal (81-A-18C) Recardina Military Functions Rule 3
The Comission unanimously approved a letter denying an appeal of the withholding of five documents regarding the decision to reconsider the rule on the military functions exception from NRC rules of procedure,10 CFR 2. 700a.
(OGC) (Subsequently, on January 22, 1982 the letter was signed by the Secretary).
2 Section 201 of the Energy Reorganization Act, 42 U.S.C. 5584.1, provides that action of the Comission shall be determined by a i
" majority vote of the members present." Comissiorier Roberts was l
not present when this item was affirmed, but had previously indicated j
his approval of the item.
Comissioner Bradford agreed not to participate in this. affirmation as an accor:raodation to the majority. Had they both
)
been present, Commissioners Bradford and Roberts would have affirmed their prior votes.
Accordingly, the formal vote of the Comission was j
2-1 in favor of tne decision.
j Section 201 of the Energy Reorganization Act 42 U.S.C. 55541 provides that action of the Co=ission shall be determined by a " majority vote of the members present."
Cemissioner Roberts was not present when l
this item was affirmed, but had previously indicated his approval of the item.
Had Comissioner Roberts been present, he would have affirmed i
nis prior vote.
Accordingly, the formal vote of the Comission was
- ~
4-0 in favor of the decision.
ENCLOSURE N f
c
-._~
~.
ITEMS APPROVED BY THE COMMISSION - WEEK ENDING JANUARY 29, 1982 B.
STAFF REQUIREMENTS - BRIEFING ON STATUS AND PLAN FOR SEVERE ACCIDENT RULEMAKING (SECY-82-1), 10:05 A.M., WEDNESDAY, JANUARY 6, 1982, j
COMMISSIONERS' CONFERENCE ROOM, DC OFFICE (OPEN TO PUBLIC ATTENDANCE),
j Memo SECY to Dircks and Remick. 1/29/82 The Commission was briefed by staff on a new approach to the i
severe accident rulemaking as described in'SECY-32-1.
The staff expects to receive standard plant designs from industry and proposed that the Commission use rulemaking to approve the specific plant designs.
The standard plants would be
. expected to meet or exceed requirements in the new CP/ML -
rule and the updated SRP.
The Commission agreed to consider substituting this approach for a generic severe accident rulemaking.
The staff was directed to revise the draft policy statement to address Commissioner comments including:
i 1.
Careful conside' ration should be given to ensuring i
that conflicting or incorrect signals are not sent I
to industry relative to significant matters that were to be contained in the long term rulemaking proceedings, e.g.,
filtered vented containment, core retention devices, hydrogen control measures, thicker basemats, and other items listed in the Action Plan.
To the extent feasible, include a list of these-items in the policy statement and say explicitly how they are to be treated in the review of new applications.
l 2.
More specific guidance pertaining to design criteria i
and minimum safety requirements considered necessary l
by the Ccmmission should be specified, e.g. stronger i
containments.
3.
Policy regarding backfitting of new requirements 4
resulting from acceptance of standardized designs should be address'ed.
f 4.
The requirements set forth in the new CP rule should be applied'to any FDA's referenced in future applications.
5.
Since the safety goal is not yet in effective form, the continued reference to and reliance on i
it should be qualified in the proposed Policy Statement.
6.
It should be emphasized that PRA is only one of several tools used in the development of safety rulemakings.
ENCLOSURE N f
J
I
- r..
I
~
ITEMS APPROVED BY THE COMMISSION - WEEK ENDING JANUARY 29, 1982 B.
Staff Recuirements (cont'd)
I References to current siting policy or practice 7.
should be supplemented by noting that work is being done to further refine the policy.
i References to one-step licensing should be qualified 8.
since the Commission has taken no action toward adoption of such a policy.
l The following statements should be deleted from l
9.
l the Policy Statement:
Pace 2:
"The Commission does not believe that, in the interim, this continuing research should be a deterrent to the placement of orders or the initiation of licensing reviews for new CP applications."
Pace 4:
... current generation light water reactors j
are estimated to be close to or below the risk levels we believe acceptable, and that..."
The new CP rule applies to only a narrow group of i
10.
CP applications.
The Policy Statement should indicate that the CP rule is at least a minimum requirement for new plants, but should not suggest l
that it will be sufficient for new plants.
j The staff should obtain ACRS input to the Policy Statement.
The revised Policy Statement should be forwarded to the Commission for approval.
(NRR/RES) (SECY SUSPENSE:
3/1/82)
The Commission also requested that, if the new policy is adopted, the staff show how:
they will ensure that IDCOR effort continues; (NRR/RES) l 1.
they will ensure that NRC research and~other 2.
programs critical to this approach are continued.
(NRR/RES)
(SECY SUSPENSE:
3/1/82) i The staff indicated that:
A paper containing plans for producing research l
information needed to confirm regulatory decisions in the severe accident area, including methodology for comparing the cost of proposed new requirements with their risk reduction, and generalized reduction in the uncertainty of PRA, will be provided to the Commission by February 25, 1982.
(RES) l l
ENCLOSURE N i
i
=
l 5
ITEMS APPROVED BY THE COMMISSION - WEEK ENDING JANUARY 29, 1982 l
l B.
Staff Recuirements (cont'd) i Technical justification concerning the need for i
severe accident features on operating plants will be available from industry '(IDCOR) and NRC studies of degraded core accidents in mid' to late.1983. (NRR/RES)
{
^
l l
A revised staff estimate of the accident source l
term, which affects siting, emergency planning and severe accident PBA will be completed in 18 months l
I l
to two years. (RES) t l
A Policy Statement on safety goals should be issued in final form by July,1982. (OPE) 1 1
l I
l 1
l l
4 i
O ENCLOh0RE N 1
I 1
I a
l 4
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
- CY-82-59 February 10, 1982 INFORMATION REPOR:
For:
The Comissioners From:
T. A. Rehm, Assistant for Operations, Office of the EDO Subjec.t: WEEYLY INFORMATION REPORT - WEEK ENDING FEBRUARY 5,1982 3
A su:: nary of key events is included as a convenience to those Comissioners who may prefer a condensed version of this report.
Contents Enclosure Administration A
Nuclear Reactor Regulation B
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 X*
Small & Disadvantaged Business Utili: ation L*
Regions M*
Items Approved by the Commission N
/
, z ! _2 Re M stant for Operatiens
} h f - W A
- i. A
^
i fd-Office of the Executive Director I
for Operations l
l
- No inout inis week.
f)
Contact:
D w.c r oN:
T. A. Rehm, CECO C:rniissioners FOR INTERNAL NRC 49-277El C:rnission staff offices DISTRIBUTION CNLY i
/
j m
510225cc3c7 '4r-
~
di 3 m
3 T2-5 6
D
/b CL
SUMMARY
OF THE WEEKLY INFORMATION REPORT Week Ending February 5, 1982 l
i l
Crystal River Unit No. 3 (CR-3)
On January 28,1982, CR-3 shut down so that the licensee could locate and repair an unidentified main coolant system leak of about 1 GPM.
The leak appears to be due to a circumferential crack in a check valve.
Leakage was also found in the reactor coolant pump second stage seal pressure sensing line. The licensee estimates that repairs will take about two weeks to complete.
West Valley Project On February 1, 1982, NFS filed an application for amendment of the West Valley facility license that would terminate the authority and responsibility of NFS under the license, subject to certain conditions.
The staff expects that NYSERDA will join the application.
New Mexico Amended Acreement NRC staff will meet with New Mexico officials on February 17 to present staff corrents on New Mexico's draf t proposal for an amended agreement for regulation of uranium mill tailings.
I FY 1983 Sucget The NRC budget justification to Congress (Green Book) has been distributed to the Commission and the staff. The Chairman held a press briefing on the FY 1983 budget on February 6,1982.
Workshop on Forecastino Electricity Demand Final preparations are under way for a workshop on forecasting electricity I
demand by State agencies.
It is being sponsored jointly by NRC and Oak Ridge National Laboratory and will be held at NRC's H Street office on February 23. This workshop is part of an overall effort to place substantial reliance on State assessments of need for power to fulfill NRC's NEPA I
responsibilities.
t
i I
OFFICE OF ADMINISTRATION l
i Week Ending February 5,1982 l
f ADMINISTRATION OF THE FREEDOM OF INFORMATION ACT STATUS OF RE0 VESTS Initial Appeal of Reouest Initial Decision Received 110 4
i Granted 31 0
Denied 7
3 4
Pending 72 1
ACTIONS THIS WEEK j
Received L. Quinlisk Requests a list of nuclear plants now operating and (22-52) those proposed in the States of Arkansas, Maine and
)
(Individuals requesting Request information regarding their Reactor Operator information about themselves)
License.
(82-53 thru 82-73)
Wayne Westlake, Requests all documents dealing with AEC license Seaweeds and exempt contractors and Department of Defense license Constructions exempt radioactive waste disposal operations from (82-74) 1946-1972.
Judith Schleicher, Requests documents regarding two accidents at Township of Isomedix in Parsippany, New Jersey in 1974 ar.d 1976.
Deville, New Jersey (82-75)
David A. Coppell, Recuests documents concerning Americium-241 alpha
{
Amerstam Corocration foil radiation sources manufactured by EAD (82-76)
Metallurgical Inc. of Tonawanda, New York.
Robert Lorei, Requests all non-compliance reports filed with the Community Radio for NRC by the operators of the Crystal River Nuclear the Tampa 8ay Area Power Plant and information on unscheduled venting (82-77) of radic:ctive material from Crystal River.
Alyssa L. Talanker Requests a list of the names and addresses of (82-78) individuals and groups from Massachusetts who have submitted FOIA requests during 1981.
CONTACT:
J. M. Felton 492-7211 EMCLOSURE A f
2 Received, Cont'd Requests documents on the investigation of Louisiana Liz Galtney, GAMBIT Newspaper Power and Light's corporate security manager, (82-79)
Wallace Friloux.
Malcolm H. Philips, Jr.,
Requests nine categories of documents regarding the Debevoise & Liberman Proposed Rule on Interim Requirements Related to (82-80)
Hydrogen Control.
Harold J. Spelman, Requests a copy of the statement by William J.
Harold J. Spelman Dircks in a December 1981 letter to Congressman and Associates John Erlenborn regarding Replacement of Wells (82-81 )
in West Chicago, Illinois by Connections to a Public Water Supply at Lindsey Chemical Company's Expense.
Lucian Kirby Paul, Jr.
Requests a copy of the technical proposal resulting (81-82) in the award of Contract NRC-10-82-356, " Operation and Maintenance of the NRC Document Control System (DCS)."
Granted Ruth E. Van Demark, In response to a request for documents identifying Wilcman, Harrold, operating licensed and/or amendments pertaining Allen & Dixon to the possession, shipping, receiving and storing (82-16) of nuclear fuels at Dresden, Quad-Cities and Zion Nuclear Power Plants, made available a reference list of 24 documents.
( An individual reouestino In response to a request for information regaroing information about himself) his Reactor Operator License exam results, mace (82-17) available the requested documents.
Steven C. Sholly, In response to a request for a copy of a memorandum Union of Concerned from Harold R. Denton, Director, NRR to NRR Scientists Division Directors, dated 7/10/81 directing that (82-26) no resources be expended on NUREG-0660 Priority 2 and 3 issues until FY 83, made available a copy of this document.
L. Quinlisk Made available two documents pertaining to operating (82-52) nuclear power plants and those proposed in Arkansas, Maine and Tennessee.
ENCLOSURE A
i 3
Denied In response to a request for documents prepared in Thomas Devine, Government Accountability connection with the Office of Inspector and Auditor's report on the Office of Inspection and Project (81-488)
Enforcenent's investigation of the Zimmer Nuclear Power Station, made available 16 documents. Denied portions of two documents, the release of which would constitute an unwarranted invasion of personal privacy and disclose the identities of confidential sources. Denied four documents in their entirety which are communications between Commissioners and their staffs and constitute advice, opinions and reconmendations. Also denied two transcripts in their entirety since the discussion focused on the review of investigatory reports and the consideration of potential enforcement actions, including the imposition of i
civil penalties, all within tne context of an l
l ongoing agency adjudication.
(NRC employee)
In response to a request for a copy of the Candidate (82-18)
Evaluation, Certification and Selection Record (CERT) for Vacancy Announcement No. 82-0429, denied portions of the CERT, the disclosure of which would constitute a clearly unwarranted invasion of personal privacy.
1 l
i ESCLOSURE A I
i f
l-DIVISION OF CONTRACTS l
Week of February 5,1982 f
RFP ISSUED 1.
RFP No. RS-RES-82-006 Title "Nemaha Ridge Seismograph Networks" l
Description - Conduction of confirmatory seismological research in the Nemaha Ridge /Mid-Continent Geophysical anomaly area. There i
will be four seismological tasks which include the installa-tion and operation with data analysis of seismographic networks in Oklahoma, Kansas, Nebraska and Iowa.
Period of Performance - 3 years with options for two additional years Sponsor - Office of Nuclear Regulatory Research Status - RFP issued on February 5,1982, Proposals due March 8,1982 IFB ISSUED 1.
IFB-RS-ADM-82-377 Title - Lease of Sedans Description - The lease of ten (10) midsize sedans for a one year period with a one year option.
Period of Performance - One year Sconsor - Office of Administration Status - CBD notice issued January 22, 1982 CONTRACT AWARDED 1.
NRC-05-82-248 i
Title - Acquisition of one (1) Multichannel Analyzer and Accessories Description - Equipment will be for routine inspections and for non-l destructive assay measurements in response to emergency situations.
Period of Performance - Within 30 days after contract award.
Sponsor - OIE Status - A fixed price contract in the amount of 57,830.00 awarded to D.S. Davidson Co., Inc.
CONTRACTS CLOSED OUT (All administrative action completed and final payment made)
CONTRACT NO.
CONTRACTOR CLOSE-0UT-DATE NRC-05-79-251 Combustion Engineering, Inc.
2/2/82 AT(49-24)-03E5 NUS Corporation 2/3/82 NRC-10-SO-361 Microtech, Industries, Inc.
2/4/82 NRC-C2-B1-059 Geotechnical Eng., Inc.
2/5/82 ENCLOSURE A f
i
\\
i 0FFICE OF NUCLEAR REACTOR REGULATION WEEK ENDING FEBRUARY 5,1982 f
CRYSTAL RIVER UNIT NO. 3 (CR-3)
On January 28, 1982 CR-3 shut down to locate and repair an unidentified main coolant system leak of about 1 GPM. On first entering the containment it was l
i f
thought that the leak was due to a gasket leak in the top flange (bonnet) in the 21/2" check valve on the make up line to the loop A reactor inlet line. This connection also serves for High Pressure Injection. When the insulation was l
removed it was found that the leak was due to a circumferential crack in check '
valve to pipe stainless steel weld on the downstream side of the check valve (i.e., en the reactor inlet side of the valve). The crack covers over one half the circumference. The licensee is making preparations to remove the weld and have it examined. The licensee has also found leakage in the reactor coolant pumo second stace seal pressure sensing line. The seal package will be replaced and tne replaced seal package will be examined to determine the exact location and cause of the leak. The licensee is estimating that the repairs will take
(
about two weeks to accomplish.
MEETING NOTICE i
Subject:
Clinch River Bre-der Reactor Loose Parts Monitoring Meeting l
Date/ Time:
February 24,1982, at 8:30 a.m.
Location:
Air Rights Building, Room 2242 Bethesda, Md.
Attendees:
J. Longenecker, D. Goeser, et. al. (DOE)
J. Mauck, D. Moran, J. Weldenhammer, R. Stark, et. al. (NRC) l i
l I
EN LOSURE B t
\\
...~
i NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT January 31, 1982 - February 6,1982
[
,l Plant Status t
Core Cooling Mode: Heat transfer from the reactor coolant system (RCS) loops to reactor building ambient.
l Available Core Cooling Modes: Decay heat removal systems.
Long '.erm cooling "B" (once through steam generator-B).
l i
RCS Pressure Control Mode: Standby pressure control (SPC) system.
i Backup Prer.sure Control Modes : Mini decay heat removal (MDHR) system.
Decay heat removal (DHR) system.
i Major Parameters (as of 0500. February 5 1982) (approximate values) l Average Incore Thermocouples : 103*F Maximum Incore Thermocouple:
135'F i
l RCS Loop Temperatures-A B
(
Hot Leg 96*F 98'F Cold Leg (1)
Bl*F 78'F (2) 89'F 83*F
{
RCS Prer.sure: 97 psig i
Reactor Building: Temperature :
60*F i
l Water level:
Elevation 284.6 ft. (2.1 ft. from floor)
Pressure:
-0.27 psig l
Air %rne Radionuclide Concentrations-2.7 x 10-7 uti/cc H3 (sample taken 2/t./82) 85 1.5 x 10-6 uti/cc Kr (sample taken 2/1/82) l Effluent and Environmental (Radioloeical) Information 1.
Liquid effluents from the THI 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 January 29, 1982, through February 4,1982, the effluents contained no detectable radioactivity at the discharge point although individual effluent sources which originated within Unit 2 contained minute amounts of radioactivity.
Cal culations indicate that less than three millionths (0.000003) of a curie of cesium was discharged.
ENCLOSURE S
-m-, -. -. -.
. 2.
Environmental Protection Agency (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.
The EPA is currently collecting environmental air samples for tritium (H-3) analysis from three sampling stations near the site and one control station near Reading. EPA has informed the NRC that the air tritium samples are being analyzed and the collected data is being reviewed and evaluated prior to publishing a report on the H-3 sampling around TMI.
The NRC will report the H-3 analytical results once they become available from EPA.
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 January 27, 1982 through February 4,1982.
3.
NRC Environmental Data.
Results from NRC monitoring of the environment l
around tne TM1 site were as follows:
1 The following are the NRC air sample analytical results for 1
the onsite continuous air sampler:
I-1 31 Cs-137 Samol e period (uti/cc)
(uti/ct)
HP-305 January 28, 1982 - February 3,1982
<8.1 E-14 <8.1 E-14 4
Licensee Radioactive Material and Radsaste Shioments.
On Thursday, February 4,1982, two drums, each containing seven SDS (Submerged Demineralizer System) samples from Unit 2, were shipped to Oak Ridge National Laboratory, Oak Ridge, Tennessee.
On Thursday, February 4,1982, a Unit 1 one liter composite sample (waste evaporator condensate storage) was shipped to Radiation Management Corporation, Philadelphia, Pennsylvania.
On Friday, February 5, 1982, 127 drums of Unit i and Unit 2 compacted LSA trash were shipped to U.S. Ecology Inc., Richland, l
1 ENCLOSURE 8 I
i r
3 Major Activities 1
Submerced Demineralizer Eystem (SDS).
Processing of batch 18 commenced on January 31, 1982, and completed on February 6,1982.
The radioactivity in the spent fuel pool water is now approximately 5.9 x 10-3 uc/ml (gross s-y activity).
The supplemental spent fuel pool cleanup system, designed to remove the radioactive materials leaked through a faulty "0"-ring at a connection to an SDS vessel on January 20, 1982, became operational on February 2,1982.
The DF for this cleanup system averaged 2.6 x 103 during the report period.
Five SDS zeolite vessels are currently stored under 23 feet of water in spent fuel pool "B".
Four of these 10 ft3 stainless steel sessels contain from 25,000 to 56,000 curies, predominately as ces i um-137, 134, and strontium-90.
One additional vessel, which was generated from processing RC bleed tank water, contains approx-imately 4,800 curies of radioactive materials. DOE has agreed to accept the 10-20 highly loaded SDS zeolite vessels for R&D disposal demonstration.
The licensee's program for handling and shipping the anticipated 10 to 20 SDS vessels is being finalized.
As expected, measurable amounts of hydrogen and oxygen gas have been detected in the spent SDS vessels as a result of radiolysis of residual water.
These zeolite vessels, which have been physically dewatered, are normally vented to an off-gas system to eliminate hazardous gas mixtures.
Radioactive containment requirements during shipment preclude continuous vessel venting during transit.
Currently GPU, with technical assistance from DOE's contractors at the Idaho National
)
Engineering Laboratory and Rockwell Hanford, is pursuing engineering i
designs to either minimize the radiolysis of water or to recombine the hydrogen and oxygen in compliance with applicable Federal Regulations. The potential engineering designs which include a vacuum drying concept and in-vessel recombiner, are being fabricated.
This work is estimated to be completed over the next four to six months.
2.
EPICOR II. The EPICOR II system continued to process SDS effluents curing tne report period.
)
3.
Reactor Buildina Entries. Two entries were made into the Unit 2 reactor building (RB) during the first week in February. Tasks completed during the entries included a load test of the polar crane mounted supports for a power lift, assembly of the power lift platform on the 347 ft. elevation of the RB, and work commenced to replace fire hoses on R3 fire stations.
An NRC. TMIPO Radiation Specialist entered the RB for an independent radiation survey and j
inspection of accessible areas. No RB entries are scheduled for the week of February 7,1982.
l ENCLOSURE 3 1
i V h TMI Unit i Developments _
1.
On February 4 and 5,1982, the NRC sponsored a workshop in McLean, Virginia, on psychological stress in the TMI area.
The participants for the workshop were 11 professional psychiatrists, psychologists and research experts with 4 additional expert witnesses and a professional facilitator to lead the discussion.
A verbatim transcript of the workshop was kept and will be available for reading in the TMIPO Middletown Office.
The Mitre Corporation is under contract to the NRC to prepare a summary report of the results of the workshop. This report should be completed in early March and will also be available in the Middletown office.
2.
The NRC has received a draft report entitled, " Chronic and Acute l
Stress Associated with the Three Mile Island Accident and Decontamination:
Preliminary Findings of a Longitudinal Study", from its contractor.
Dr. Andrew Baum, a medical psychology professor at the Uniform Services University.
The draft report concluded that residents in the TMI area experienced low but measurable levels of stress when I
compared to control groups in other areas. The draft report is available for reading in the Middletown office.
f i
i i
ENCLOSURE B I
-5 Future Meetings 1.
On Friday, February 25, 1982, Lake Barrett will be speaking for the dinner meeting being held by the Engineers Week Joint Planning Council to honor Lehigh Valley's Engineer of the Year and Young Engineer of the Year.
2.
On Saturday, March 13, 1982, Lake Barrett will address the Society of Manufacturing Engineers in Williamsport, PA, on the cleanup of TMI and general aspects of nuclear power.
1
(
i i
1 i
l ENCLOSURE S i
e
i I
I.
OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending February 5,1982 Meetina with Natural Resources Defense Council A meeting was held on January 27, 1982, with the Natural Resources Defense.
Council to explain provisions of the MC&A Reform Amendments. Other public interest groups had been invited, but were unable to attend. The meeting was useful for clarifying some of NRDC's questions about the Reform Amend-ments and for presenting the Safaguards staff with NRDC's perspective on some of the issues involved.
KERR-MCGEE A meeting was held on February 2,1982, with Kerr-McGee to discuss pro-cessing of waste residues at the Sequoyah UF6 conversion plant.
Kerr-McGee described their future plans for the processing and disposal of lagoon sludge at their Sequoyah facility. Pilot studies have indicated that by calcining the sludge, Kerr-McGee can get a volume reduction of approximately 80% and end up with a residue that contains aporoximately 1-1/2% uranium which may be suitable for processing at their uranium mill. This preliminary discussion was to get the staff'c opinion on their proposed plant processing design and any comments on proposed methods of transport.
Meeting with Combustion Engineering A meeting was held on January 27, 1982, with Combustion Engineering, Inc.
(CE) representatives to discuss shortcomings in CE responses to NRC comments on their SNM-1067 license renewal application. Most of our comments were resolved. However, CE desires to review further several recommendations made for their radiation safety program and is completing a nuclear criticality safety analysis to justify some of the criteria that differ from those in their present license.
The subsequent meeting with CE has been scheduled for March 1982 to discuss any outstanding questions relating to their license renewal application.
Meeting with Westinghouse A meeting was held on February 2 and 3,1982, with Westinghous'e to discuss preliminary safety analysis and schedule for licensing a new UF6 dry con-version line for the production of UO2 fuel assemblies.
At the conclusion of the meeting, additional information on geometric con-i figurations on processing equipment, limited process parameters, chemical ano physical properties of the UOp and process additives. and details of KEND calculations based on such informacion were identified as being necessary for the NRC review. Westingnouse had left this information out of the draft safety document because it may be proprietary (the process is licensed by BNFL) and may recuire BNFL permission to submit it to NRC. Westinghouse plans to initiate procurement of the equipment by the end of 1982 end needs NRC agreement on the adequacy of the moderation controls prior to procurement.
ENCLOSURE C f
2 West Valley project On February 1,1982, NFS filed an application for amendment of the West Valley facility license that would terminate the authority and responsi-bility of NFS under the license. Such termination would be effective upon (1) acceptance of surrender and assumption of responsibility for the facility by NYSERDA (presently a co-licensee with NFS); (2) DOE's assump-tion of exclusive possession and control of the facility; and (3) the settlement date of an agreement to be made between the co-licensees resolving the dispute now being litigated in the U.S. District Court of the Western District of New York. The application indicates that NYSERDA and DOE support the application and that NYSERDA, by separate letter, will join in the appli-cation.
It is the staff's understanding that NFS and NYSERDA are nearing, or have reached, agreement on their dispute and that filing of the supporting letter by NYSERDA is imminent.
Society of Nuclear Medicine Committee Meetina On January 26, 1982, Dr. William Walker, representing the Division of Fuel Cycle and Material Safety, attended a meeting of the Society of Nuclear i
Medicine's Committee on the Legislative Relations in Phoenix, Arizona. This meeting was in conjunction with the Annual Society of Nuclear Medicine Executive Committee Meeting.
Dr. Walker presented an outline of NRC's planning under-way for the proposed revision of the medical licensing process. There was much interest among the attendees and reaction to the anticioated approach was f avorabl e.
This approach includes: recodification of 10 CFR ?", development of a simplified medical licensing application form and computet 1:ation of j
naterial licensing functions, i
l l
i l
ENCLOSURE C i
l
Meetines - Division of Waste Manacement I
1 1.
Subject:
Discussion of comments of regulatory departments of the United Kingdom on proposed 10 CFR Part 60 Date/ Time:
February 7-8, 1982 Location:
London, England i
Attendees:
F. S. Feates, Department of Environment, London; Dr. Michael J. Bell, WMHL 2.
Subject:
Participation in Steering Committee for Nuclear Energy Meeting Date/ Time:
February 10-11, 1982 l
Location:
Paris, France Attendees:
Radioactive Waste Management Committee, Paris-i Dr. Michael J. Bell, WMHL Absences of the Director / Deputy Director None l
r 4
j i
1 1
ENCLDSURE C I
l Meetines - Division of Fuel Cycle and Material Safety 1.
Subject:
Review design of NFS ventilation modifications and review EIA for Kerr-McGee fertilizer use with ORNL.
Date/ Time:
February 3-4, 1982 Location:
Spartanburg, South Carolina and Oak Ridge, Tenneseee Attendees:
W. A. Nixon (NMSS) and Representative from Region II 2.
Subject:
Observe fuel handling facilities (BWR)
Date/ Time:
February 5,1982 i
Location:
Peach Bottom, Pennsylvania Attencees:
G. H. Bidinger, N. Ketzlach and B. L. Serini (NMSS),
Resident Inspector and representatives from PA Electric Company.
3.
Subject:
Briefing to be given to Congressman Corcoran on Kerr-McGee, West Chicago.
Date/ Time:
February 8, 1982, 2:00 p.m.
Location:
Congressman's Corcoran's Office, 1107 Longworth House Office Building Attendees:
J. G. Davis, R. G. Page W. T. Crow, W. A. Nixon (NMSS) and Representatives from ELD and CA.
c.
Subject:
To participate in the workshop of the New York Academy of Medicine to discuss low-level institutional waste.
Date/ Time:
February 8-9, 1982.
Location:
New York Attendee:
Lidia A. Roche (NMSS) 5.
Subject:
Meeting with Steven Kraft of Edison Electric to discuss i
GESFD.
Date/ Time:
February 19, 9:00 a.m.
Location:
Room 552, Willste Building Attendees:
R. E. Cunningham and Homer Lowenberg (fW.SS) and Steven Kraft, Edison Electric i
I 6.
Subject:
Meeting with New England Nuclear and IEAL to discuss Licensing Management System.
Date/ Time:
February 19, 1982, 9:00 a.m.
Location:
Room 566 Willste Building Attendees:
T. F. Carter, Jr. (NMSS) and Representatives from IEAL and New England Nuclear.
Absences of the Director and Deputy Director None ENCLOSURE C
i 4
Planned Meetines - Division of Safecuards i
1.
Subject:
Changes to Security Plan Date: Feb. 3 Location: Silver Spring, Md.
Attendees: Susquehanna Steam Electric Station NRR Progran Manager C. Gaskin 2.
Subject:
73.55 Plan Review and initial site visit Date: Feb. 4-5 l
Location: Perry Nuclear Plant Attendees: Applicant D. Kunze 3.
Subject:
73.55 Plan Review and initial site visit Date:
Feb. 16-18 Location: k'olf Creek Nuclear Plant Attendees: Applicant D. Kunze 4.
Subject:
Miles /Less Program (Meeting with Sandia Laboratories)
Date:
Feb. 17-18 l
Location: Silver Spring, Md.
Attendees:
L. Chapman, Sandia J. Cawley L. Ouinn J. Hockert S.
Subj ect: Meeting with BG&E security organization staff and safeguards staff to conduct a site tour and to obtain information to be used in the development of licensee guidance on screening crograms.
Date:
Feb. 9 Location: Calvert Cliffs Nuclear Facility Attendees:
R. fiayer, BG&E T. Allen, SGPR J. Metzger, SGPR N. Paradiso, SGPR P. Dwyer, SGPR 6.
Subject:
Meeting with -Stress Control, Inc., New York to observe I
a series of psychological clinical interviews to assist j
in the developrent of licensee guidance on screening programs.
Date:
Feb. 12 Location: New York, New York Attendees:
T. Allen, SGPP J. Metzger, SGPR P. Dwyer, SGPR Members of Stress Centrol, Inc.
ENCLDSURE C I
l l
2-7.
Subject:
Cor:municated Threat Credibility Assessement Project Date: Feb. 16 l
Location: Silver Spring, Md.
Attendees:
G. Moore, LLL J
L. Quinn P. MacMurdy Absences of the Director and Deputy Director R. F. Burnett - February 16-19,1982 (Annual Leave) l Acting:
D. R. Chapell I
i l
l i
i i
I I
EMCLOSURE C f
i 0FFICE OF INSPECTION AND ENFORCEMENT ITEMS OF INTEREST February 1,1982 to February 5,1982 1.
There were no Significant Enforcement Actions imposed during the past week.
2.
Preliminary Notifications relatino to the following actions were dispatched during the week:
a.
PNO-I-82-09D and 09E, R. E. Ginna Nuclear Power Plant - Steam Generator Tube Ruoture, Updates.
b.
PNO-I-82-13, Maine Yankee Atomic Power Co. (Maine Yankee) - Plant Design Erro r.
c.
PNO-I-82-14, Public Service Electric and Gas Co. (Salem Unit 1) - Failed t
Fuel Pin.
d.
PN0-I-82-15, Public Service Electric and Gas Co. (Salem Units 1 and 2) -
Spill of Contaminated Water and Contamination of Personnel.
e.
PNO-II-81-114A, Virginia Electric and Power Co. (Surry Units 1 and 2) -
Security Force Terminations at Surry and Resultant Media Attention.
f.
PNO-II-82-13 and 13A, Florida Power Corp. (Crystal River Unit 3) -
Unplanned Outage.
g.
PNO-II-82-la, Alabama Power Co. (Farley Unit 2) - Unplanned Outage.
h.
PMO-II-82-15, Florida Power and Light Co. (Turkey Point) - Alleged On-Site Use of Drugs.
i.
PNO-II-52-16 Florida Power and Light Co. (Turkey Point Unit 4) - Unclanned Outace in Excess of Two Days.
k.
PNO-III-82-11 A, Consumers Power Co. (Palisades) - Ooerational Problem Resulting In An Outage Which Is Expected To Last Longer Tnan Two Days.
1.
PNO-III-82-13A, Commonwealth Edison Co. (Zion) - Videotaped Threats Acainst Zion Received By Chicago News Media.
m.
PNO-III-82-14 American Electric Power Service Corp. (D. C. Cook) - Turbine Trio Due to Vibration.
PNO-III-82-15, Consumers Power Co. (Palisades) - Operational Problem Resulting n.
In The Automatic Initiation Of The Safety Injection System And A Manual Trio Of All Reactor Coolant Pumps.
ENCLOSURE D m
l o.
PNO-III-82-16, Consumers Power Co. (Palisades) - Hydrogen Leak On Main Generator, Explosion, Fire, and Personnel Injury.
p.
PNO-IV-82-02, Kerr McGee Nuclear Corp. (Seoucyah - Uranium Conversion Facility) - Release of Radioactive Material to Unrestricted Areas As A Result of Pipe Rupture.
a.
PNO-IV-82-03, Analytic Inspection, Inc. (Licensee of State of Louisiana) -
Offshore Radiograpny Exposure.
r.
PNO-IV-82-04, Omaha Public District (Fort Calhoun Unit 1) - Release of Waste Gaseous Products During Samoling.
s.
PNO-IV-82-05, General Atomic Co. (San Diego) - Leakinn Shipment of Radioactive Material.
3.
The following IE Infomation Notices have been issued:
a.
IE Information Notice No. 82 Auxiliary Feedwater Pump Lockout Resulting From Westinghouse W-2 Switch Circuit Modification was issued on January 25, 19E2 to all power reactor facilities holding an operating license or construction Demit.
b.
IE Infomation Notice No. 82 Westinnhouse N8FD Relay Failures In Reactor Protection System At Certain Nuclear Power Plants was issued on January 27, 1982 to all power reactor facilities holding an operatinq license or construction pemit.
4.
Other Items a.
Payment of Civil Fenalty - On February 3,1982, NRC received payment in full of ',1,000.00 from Nuclear Diagnostics, Inc. for civil penalty imposed on Dacer.ber 30, 1981.
b.
The Deputy Director of the Division of Emergency Preparedness participated in a meeting with INP0 on February 3,1982, to discuss integration of both NRC and IMP 0 emergency preparecness programs.
I c.
Members of the Ouality Assurance Branch met with representatives of the FAA on February 4,1982 to discuss quality control measures used by the FAA.
l ENCLOSURE D l
i
C
', f 0FFICE OF NUCLEAR REGULATORY RESEARCH l
t IMPORTANT EVENTS FOR THE WEEK ENDING FEBRUARY 5,1982 j
Experimental Procrans Branch j
I 1.
BWR Full Intectal Sinulation Test (FIST)
GE has now completed the forral proposal for the Phase II of the FIST program and has forwarded it to NRC and EPRI. This proposal l
was delayed approximately 1 month due to changing cost estimating l
factors (overhead, escalation, etc.). It is anticipated that a PM3 meeting will be held the first week in March to review the proposal.
2.
Data Bank More data from the Swiss NEPTUN Facility were added to the data bank: 5006, 5007, 5003, 500% 50011 and 50012. These data pertain to core boiloff experiments to check the effect of clad thermocouples An intermediate break test, 5-IB-01, the first from en rods.
l a new series of Semiscale tests, was added and is presently password l
Data from PBF test, on LOFT 1ead rod 4A, was also entered protected.
into the data bank.
3.
Semiscale i
A series of tests has been scheduled for March through June. Included i
are two steam generator characterizations' tests, three feedwater line breaks (100 percent, 50 percent and 14 percent), and three l
steam line breaks (100 percent with loss of power,100 percent with power available, on srall break with detail to be determined).
We are also evaluating the need for and usefulness of a Ginna transient simulation.
4 Bundle Heat Transfer Evaluation On December 18, 1981, a letter requesting rod bundle heat transfer data was sent to various international agencies. Responses have l
been received from organizations in Italy, Japan and England. Each has expressed their willinoness to provide,and locate heat transfer data for correlation, evaluation and development.
l l
Severe Accident Assessment Branch The Large Melt Facility (LMF) large scale fuel test is scheduled for the 1.
week of February 22-26, 1982. A final preparatory test with a glass charge is to be tested the week of February B-12.
Both fluidic thermometry and ultrasonic thermometry will be installed for final calibration and operational check. LANL has completed the finish machining of the Ta-10w crucible and final welding will be completed February 10 to 12.
ENCLOSURE E f
l
Fuel Behavior Branch 1.
Marviken Aerosol and Fission Product Transport Tests R. Sherry /FBB attended a 3-day planning meeting (1-20/1-22) at Norrkoeping, Sweden on the proposed aerosol and fission product RCS transport test program at the Marviken test facility. Twenty-two people representing ten countries (in addition to Studsvik/Marviken personnel) attended the meeting. The meeting was quite successful from the standpoint that program planning activities and schedules follow almost exactly the recommenda-tions set forth in the joint NRC/EPRI (Bassett/Lowenstein) to Studsvik l
(Collen) letter. As recommended by NRC/EPRI, four working groups (1)
Aerosol and Fission Product Generator Techniques (2) Test Parameter Measurement Technique, (3) Accident Sequence / Test Conditions, and (4)
Model Assessment Data Needs Identification, have been established to aid Marviken personnel in preparing a final program plan by June 1,1982.
Studsvik will in parallel prepare a revised cost esticate and proposed cost sharing formula for the project. The revised program plan, cost estimates, and funding arrangements will then be discussed at a meeting scheduled for mid-July. Project initiation (pending final project approval and finalization of cost sharing arrangements) is scheduled for late summer /early fall.
Analytical Models Branch 1.
LANL has released two reports on Developmental Assessment of TRAC-PF1, comparing the code with SBLOCA data from Semiscale-MOD 3.
LA-TDA/PF1-TN-82-2 shows comparison of TRAC-PF1 with data from test 5-SB-P1, while LA-TDA/PF1-TN-82-3 shows comparison with test S-SB-P7.
2.
NRC has received from LANL TRAC post-test predictions for SCTF tests S1-07 (Run 513) and 51-0S (Run 514). These tests are the power-shape effects tests. These results will be presented at the next 2D/3D Coordination Meeting in Japan.
3.
LANL has transmitted two reports on data transmittal of TRAC results under tue 2D/3D Program (LA-2D/3D-TN-81-35 and TN-82-1). These reports detail the agreements worked out with Japan and will serve as the basis fer discussion with Germany.
i 4,
Taiwan Power Company agreed by telephone to honor our request for Kuosheng's SRV test data.
5 A meeting was held on Friday, January 29, 1982 with G. Holman, the liaison from LLL at Karlsruhe, FRG, for the HDR Containment test program. GRS's request for expanding the scope of our participation, over what was agreed on earlier, was discussed. Because of limited resources and high priority issues which our contractor is participating in, we could not grant the request.
ENCLOSURE E I
J ITEMS OF INTEREST 0FFICE OF INTERNATIONAL PROGRAMS WEEK ENDING FEBRUARY 5,1982 i
l Foreien Visits to NRC On Monday and Tuesday Professor Adolf Birkhofer of the German Society for i
Reactor Safety (GRS) and Dr. Dankward Struwe of Karlsruhe met with RES Director-Robert Minogue, Charles Kelber, Deputy Director of the RES Division of Accident Evaluation, other senior RES staff, P. S. Check, Director of the CRBR Program j
Office of NRR, and IP Deputy Director J. D. Lafleur to discuss various aspects of breeder reactor risk analysis. The visitors 'also met with I. Villaiva of IE i
for a briefing on the incident at Ginna.
This week Mr. Hidetoshi Ukawa, Director General for Science and Technology Affairs. Japanese Ministry of Foreign Affairs, and the current Chairman of the IAEA Board of Governors, accompanied by First Scientific Secretary Miyabayashi l
ano Hirosni Fukuda, Counselor, of the Japanese Embassy, met with Chairman Palladino and Commissioners Gilinsky, Bradford, Ahearne and Roberts. Discussion topics included current nuclear issues such as reprocessing and waste disposal l
as well as IAEA safeguards.
l i
I l
i I
i l
ENCLDSURE G f
l f
I f
I
- Foreign Reports The following foreign reports were received in IP February 1-5, 1952:
(For further information contact Eva Szent-Ivany, IP, X27788.)
l From Canada:
AECL-7153 Final Safety and Hazards Analysis for the Battelle LOCA Simulation Tests in the NRU Reactor **
From France:
i DSN-479 Lesson Learned from Operational Experience and Most Important Incidents Occurring at French or Foreign Plants (Sent for translation.)
From Japan:
JAERI-MEM3 9718 SCFT Core-I Results (Systen Pressure Effects on Reflooding Phenomena)**
JAERI-MEMO 9731 CCTF Core-I Test Results**
l l
PNC - Development of Power Reactors and Nuclear Fpels**
PNC - News Reports, No.4 - July 1981**
l STA - Its Roles and Activities 1931**
Research and Development on Sodium Heated Steam Generators **
Japanese Planning Policy of Safeguards System Fron Sweden:
Quarterly Report - July-September 1981 (Sent for translation)
Deleted from PDR copy
- Indicates the reports are in English ENCLOSURE G f
OFFICE OF STATE PROGRAMS ITEMS OF INTEREST WEEK ENDING FEBRUARY 5, 1982 Steve Salomon attended a workshop on the packaging, transportation and disposal.of radioactive materials organized by Chem-Nuclear Systems, Inc., in Columbia, South Carolina, February. 2-4,.~ 1982.
State and Federal regulations were. reviewed and discussed.
An integral part of the workshop included a visit to the Barnwell disposal. site.to. observe and discuss the inspection, off-loading and burial of the vastes.
The new high integrity con-tainers made from cross linked polyethylene with a burial life-time of 300 years were discussed.
l Frank Young attended an Executive Board meeting of.the Conference of. Radiation. Control Program Directors.in New Orleans, Louisiana February 3-5 to discuss the overall planning of the Conference's activities, including its annual meeting which will be held May 24-27 in Portland, Maine.
A meeting has been schedbled for Febrbary 17 with New. Mexico.
officials to present NRC comments on the draft proposal for an amended agreement for regulation of uranium mill tailings.
Staff members from SP, NMSS, ELD and Region IV will participate.
l Final preparations are under way for.a workshop of forecasting electricity demand by State agencies.
It is being sponsorea 4
jointly by NRC and Oak. Ridge National. Laboratory.
The workshop and is being. held at H Street.
A is scheduled for February 23,ials who are using econometric.and selected panel of State offic mathematical models to assess need.for power in regulating and licensing decisions will present su=maries of the models and experiences.
The. panel will_then evaluate the various models.
The workshop is part of an overall effort to place substantial i
reliance on State assessments of need for power to fulfill NRC's NEPA responsibilities.
I i
l i
ENCLOSUE H
i OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS l
Items of Interest WEEK ENDING FEBRUARY 5,1982 Publication "Sumary Information Report" NUREG-0871 Vol.1, No.l. was printed and will be distributed the week of 2/8. This docu-ment contains general historical information on NRC's programs primarily emphasizing data on power reactors.
l I
)
E!iELOSURE I I
Office of the Controller Item of Interest Week Endine February 5, 1982 FY 1983 Budget l
The NRC budget justification to Congress (Green Book) has been distributed to the Commission and the staff.
A press briefing on the FY 1983 budget was held on Saturday, February 6, 1982.
Enclosure J f
I
1 ITEMS APPROVED BY THE COMMISSION - WEEK ENDING FEBRUARY 5, 1982 A.
SECY-81-700 - SECTION 203 REPORT TO THE CONGRESS ON ABNORMAL OCCURRENCES FOR JULY-SEPTEMBER 1981, Memo SECY to Dircks, 2/2/82 This is to advise you that the Commission (with all Commisshmers approving) has approved the proposed report to the Congress, subject to the following modifications /cc=ments:
l '., Section 81-3, Misalienment of High Head Safety Injection Isolation Valve (Beaver Valley)
The write-up should be consistent with the final, approved FRN (SECY-81-68 6).
In addition, the two following changes should be made:
Section on Nature and Probable Consequences, 2d a.
paragraph:
Add sentence after third sentence ending in " flow path" to read as follows:
"It should be noted that with the suction valve shut, the high head safety injection pumps could possibly have been damaged had they been operated."
i b.
Section on Cause or causes - Change wording to l
read as follows:
" Careful consideration of availdde information has led the NRC to conclude that the mispositioned valve and missing chains and padlocks were possible acts of sabotage, rather than operaer errors."
- 2., page 8 - Under Cause or Causes add a statement saying the level gauge indicators in the Control Room could have been used to determine whether the shutter was shielding the source.
- 3., page B - Under Actions Taken to Prevent Recurrence, sub-paragraph, NRC - The second sentence shculd re replaced by the following words:
"Possible enforcement action is under review; to date, the licensee has not been cited based on the section of the Interim Enforcement Policy which states, in part, l
that licensee will not ordinarily be cited for violatian resulting from matters not within their control that could not have been reasonably foreseen.
The NRC has since amended the license to make further events of this nature subject to a civil penalty."
4.
For the next AO report, Diablo Canyon should be included (using Criterion 43).
5.
The next AO report should contain the Asiatic Clams problem as either an Abnormal Occurrence or Appendix C icem.
ENCLOSURE N I
ITEMS APPROVED BY THE COMMISSION - WEEK ENDING FEBRUARY 5, 1982 A.
SECY-SI-700 (cont'd)
With respect to the Agreement State Abnormal Occurrence AS 81-2, Ccemissioners Bradford and Ahearne have posed the following questions:
a.
What are the training requirements for radiographers in Louisiana and what is OSP's assessment of this particular licensee's program?
b.
Has an information notice or circular been sent to other Agreement States and licensees regarding this event?
c.
What is the basis for allowing Agreement States to c
make their own determination of which events are Abnormal occurrences?
The Office for Analysis and Evaluation of Operational Data was informed of this action by telephone on February 2, 1982.
It is requested that you:
1 (1)
Forward the report and letters of transmittal to the Congress, as modified, to the Office of the Secretary for signature by the Chairman.
(SUSPENSE:
c.o.b. February 11, 1982).(h50D)
(2)
Forward a response to Commissioner Bradford and Ahearne's cuestions.
(SUSPENSE:
c.o.b. February 19, 1982).($f)
B.
STAFF REOUIREMENTS - AFFIRMATION SESSION 82-3, 4:05 P.M., THURSDAY, l
JANUARY 28, 1952, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE), Memo SECY to Dircks, Karnerer, 2/3/82 I
l SECY-62 General License for Mill Tailines in Acreement States The Commission approved a revocation of a general license issued on Novetter 10, 1981, to allow persons licensed by an agreement state to prc:ess uranium ore to also process uranium mill tailings.
The C:n-issien ret;uested:
1 the r deral Eegister notice te revise; as in the 1/20/82 03C e
e. rar.d.: ; ar.d (EDO)
(SECY Sus;ense: 2/10/S2)
ENCLOSURE N I
i i
~
ITEMS APPROVED BY THE COMMISSION - WEEK ENDING FEBRUARY 5, 1982 B.
STAFF REQUIREMENTS (cont'd) 2.
that the Subcomittee on Energy and the Environment, Subcommittee on Nuclear Regulation, Committee on Energy and Power, and the Subcommittee on Environment, Energy and Natural Resources be notified.
(OCA/ ELD)
(SECY Suspense: 2/10/82)
The Commission charged to OCA the responsibility of overall notification of appropriate Congressional members and staff.
C.
SECY-82 FIRE PROTECTION RULE SCHEDULES AND EXEMPTIONS (QUARTERLY REPORT NO. 4), Memo SECY to Dircks. 2/8/82 This is to advise you that the Commission has approved (by a 5-0 vote) the granting of exemptions to 10 CFR 50.48 schedular requirements as outlined in SECY-82-13.
The Cc= mission (with Chairman Palladino and Co=missioners Ahearne and Bradford concurring) has also agreed with Commissioner Ahearne's comments on SECY-82-13.
You are therefore directed to forward the generic letter to licensees to the Cc= mission for review.
You should also increase the resources applied to this program for reviewing the reports required by the NRC.
(NRR) (SECY SUSPENSE:
2/19/82)
In addition, the Co=ission (with Chairman Palladino and Cc=issioners Bradford and Ahearne concurring) has asked l
that an information paper be prepared discussing the staff's program plan and plant-by-plant schedule for assuring compliance l
with fire protection requirements, licensee conditions, and l
SER commitments.
The plan should cover all plants and i
assure that even those plants which have not sought exemptions, but have submitted inadequate and incomplete information, have an enforceable obligation to furnish the needed fire protection information by a specified date.
M (SECY SUSPENSE:
3/1/82) i
%5 l
l ENCLOSURE N l
I 1
l I
-.