ML20137B591
| ML20137B591 | |
| Person / Time | |
|---|---|
| Issue date: | 01/09/1986 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-860103, NUDOCS 8601150580 | |
| Download: ML20137B591 (27) | |
Text
. NL i
a
- January 9, 1986 For: The Commissioners From: T. A. Rehm, Assistant for Operations, Office of the ED0
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING JANUARY 3,1986 A summary of key events is included as c. convenience to those Commissioners who may prefer a condensed version of this report.
Contents Enclosure Administration A Nuclear Reactor Regulation 8 Nuclear Material Safety and Safeguards C Inspection and Enforcement D Nuclear Regulatory Research E Executive Legal Director F*
International Programs G State Programs H*
Resource Management I*
Analysis and Evaluation of Operational Data J Small & Disadvantaged Business Utilization & Civil Rights K* ,
Regional Offices L*
CRGR Monthly Reports M*
Executive Director for Operations N*
Items Addressed by the Commission 0 :
Meeting Notices P Proprietary or Other Sensitive Information (Not for Q :
external distribution)
- No input this week.
[
7
/T. A. Rehm, J QAs ant for Operations Office of the Executive Director for Operations
Contact:
T. A. Rehm, EDO .
492-7781 8601150500 860109 PDR COMMS NRCC WEEKLYIWOREPT PDR g
HIGHLIGHTS OF WEEKLY INFORMATION REPORT
'* WEEK ENDING JANUARY 3, 1986-h .
~
! TMI-1 On December 18, 1985, the Appeal Board affirmed the Licensing Board decisions on Training and Diekamp Mailgram issues. The Commissioners
- now have 40 days to act on this decision. If the Commission takes no action after 40 days, the TMI-1 Restart Proceedings will be officially concluded.
s
- Peach Bottom Atomic Power Station. Unit 2 i Unit 2 scrammed from 44% power on low reactor water level at 2
- 12 p.m.
on 12/26/85. The cause of the level decrease was the loss of 'A' <
- reactor feed pump (RFP) on overspeed trip combined with feedwater level '
control system fluctuations. At the time the 'B' and the 'C' RFPs were
! being swapped to troubleshoot RFP and level control instabilities l identified during the reactor startup on 12/25/85. During the swapping l
of B and C pumps, the RFP check valves slamed three or more causing a '
hydraulic transient in the RFP suction piping. The hydraulic transient '
resulted in the shearing off of a 1 inch drain line on the 20 inch i suction piping to the 'C' RFP, causing a steam and water leak in the turbine building. The operators isolated the condensate and feedwater j systems, and this action stopped the leak. The RCIC system was -
manually started to control reactor water level. There was no i
radioactive release from the leak. No personnel contamination i occurred. The licensee is inspecting the condensate and feedwater
, systems, and initiating repairs.
/ Limerick j The Philadelphia Electric Company announced on December 23, 1985 that the '
i company's Board of Directors had approved a decision to complete
, construction of Limerick Unit 2 under the terms and conditions of the cost -
- containment and operating incentive plans as set forth in the Pennsylvania '
l Public Utility Commission's Order of December 5, 1985.
k j Construction will be resumed as promptly as possible. Construction is
- projected to be completed by early 1991 at a total cost of approximately
- $3.2 billion, including the $894 million expended as of November 30, 1985, I at which time the unit was approximately 30% cc,mplete.
1 Unit I reached the 100% power level,1111 MWe, for the first time on December 26, 1985 and is continuirg with its startup testing program.
l l
NFS-Erwin
! As of January 2, 1986, the Labor Strike at NFS/Erwin is continuing. No date i has been set for further negotiation.
An Enforcement Conference concerning the recent incident of a handgun having been taken into the NFS/Erwin protected area is scheduled for Tuesday, January 7, 1986 at Region II. A Safeguards representative will attend.
M 3 E86 t
\
i6
. OFFICE OF ADMINISTRATION Week Ending January 3, 1985 ADMINISTRATION OF THE FREEDOM 0F INFORMATION ACT '
STATUS OF REQUESTS Initial. Appeal of
' Request Initial Decision Carryovers, 1985 181 15 Received, 1986 0 0 Granted 2 0 Denied 2 0 Pending 177- 15 ACTIONS THIS WEEK Received, 1985 Robert Todd Requests copies of all records pertaining to " unusual (85-848) events," possible security threats, and violation of airspace at the Indian Point nuclear power plant on or about July 24, 1984, with regard to a newspaper article about a sighting of a UFO over the plant.
Martin Rosenberg, Requests copies of the final OI investigative reports The Kansas City on the quality first program at the Wolf Creek nuclear Times power plant.
(85-849) .
Granted E.F. Kurtz, In response to a request for a'. listing and copies of the Duquesne Light NRR Office Letters; made. available ,103 records.
(85-726)
Thomas C. Houghton, In response to a request for copies of certain Reactor KFC, Inc. Operator and Senior. Reactor _ Operator license examination (85-771) question and answer keys, made available eight records.
Billie P. Garde. In response to a request for all requests by the' Atomic Government Safety and Licensing Board to establish a second docket Accountability in the Comanche Peak operating license hearing to hear Project the issues of harassment and intimidation, informed the (85-807) requester that the NRC has no records subject to this request.
Sally Bourgeois, In ' response to a request for copies of all records Lakeview Radiation related to Docket.40-7233 Lakeview Uranium Reduction Education Council Plant, including the final AEC Inspection' Report of (85-824) May 1965, informed the requester that the NRC has no records subject to this request.
ENCLOSURE A CONTACT: . Donnie H. Grir.sley
.492-7211 JAN 1 303
i 2
Granted, Cont'd l Kathryn H. Urban, In response to a request for a list of NRC licensees l Cintichem, Inc. for program codes 02201 and 02110, made available the (85-827) requested list.
Denied Patty Day, In response to a request for records relating to the NUS Corporation historical background of 10 CFR 50.59, made available (85-640) 11 records. Denied one record in its entirety, release of which would tend to inhibit the open and frank exchange of ideas essential to the deliberative process.
Nina Bell, In response to a request for four categories of records Nuclear Information related to quality control at the Callaway nuclear power and Resource plant, made available 11 records. Informed the Service requester that cae additional record subject to this
(85-655) request is already available at the PDR. Denied 36 records in their entirety because they contain predecisional advice, opinions, and recommendations of the staff and disclosure would interfere with m enforcement proceeding. Denied portions of th ee records, release of which would constitute an unwarranted invasion of personal privacy and disclose the identity of a confidential source.
ENCLOSURE A JAN 0 :SSS
I
-9 WEEKLY INFORMATION REPORT DIVISION OF CONTRACTS WEEK ENDING JANUARY 3, 1986 PROPOSALS UNDER EVALUATION RFP No.: RS-ADM-86-217
Title:
" Acquisition Training"
Description:
The contractor shall present the " Acquisition Training" to NRC technical employees responsible for monitoring contractual arrangements. Course materials will be provided by the NRC.
4 Period of Performance: Two years Sponsor: Office of Administration Status: RFP closed on January 3, 1986. Proposals forwarded to Source Evaluation Panel for review on January 3, 1986.
RFP No.: RS-ORM-85-335
Title:
" Integrated Library System"
Description:
Software maintenance, support and timesharing services for the Integrated Library System.
Period of Performance: Two years with one option year.
Sponsor: Office of Resource Management Status: The competitive range has been established and negotiations are scheduled for the week of January 6, 1986.
RFP No.: RS-SDB-85-387
Title:
" Development of Business Opportunities for High Technology Small Business Firms with the U.S. NRC" '
Description:
The contractor shall analyze the nature of the prime contract and subcontract market within the nuclear arena to establish a comprehensive listing of small business firms, including 8(a) firms, capable of performing NRC's technical requirements.
Period of Performance: One year Sponsor: Office of Small and Disadvantaged Business Utilization / Civil Rights Status: Best and Final offers received on December 23, 1985 and forwarded to Source Evaluation Panel for review on December 23, 1985.
CONTRACTS AWARDED RFP No.: RS-ADM-86-255
Title:
" Office Moving"
Description:
Requirements contract for NRC Inter and Intra Building moving services.
Period of Performance: December 20, 1985 through September 30, 1986.
Sponsor: Office of Administration Status: Fixed Price Requirements Contract No. NRC-10-86-255 awarded to SBA/ Alliance Moving & Storage, Inc., in the estimated amount of $70,000, ef fective December 20, 1985. This firm has been certified by the Small Business Administration as a socially and economically disadvantaged firm eligible for noncompetitive awards under that agency's 8(a) program.
J ENCLOSURE A JAN 0:CCS L.
Weekly Information Report Division of Contracts
- CONTRACTS AWARDED (cont'd)
RFP No.: RS-ORM-85-316
Title:
"NRC ADP Systems"
Description:
Services to maintain and improve automated information systems managed by the Office of Resource Management.
Period of Performance: Three years Sponsor: Office of Resource Management Status: Indetinite Delivery Type Contract No. NRC-33-86-266, with provisions for Fixed Price / Cost-Plus-Fixed-Fee / Labor Hour Task Orders, awarded to SBA/Technassociates, Inc., in the estimated amount of $6.623,727 ef fective December 20, 1985. This firm has been certified by the Small Business Administration as a socially and economically disdvantaged firm eligible for noncompetitive awards under that agency's 8(a) program.
i ENCLOSURE A JAN 3 386 .
t 0FFICE 0'F NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending January 3, 1986 l l
TMI-1 On December 18, 1985, the Appeal Board affirmed the Licensing Board decisions on Training and Diekamp Mailgram issues. The Comissioners .
now have 40 days to act on this decision. If the Commission takes no i action after 40 days, the TMI-1 Restart Proceedirgs will be officially ?
concluded. i l Peach Bottom Atomic Power Station, Unit 2 Unit 2 scramed from 44% power on low reactor water level at 2:12 p.m. !
. on 12/26/85. The cause of the level decrease was the loss of 'A' ,
reactor feed pump (RFP) on overspeed trip combined with feedwater level [
control system fluctuations. At the time the 'B' and the 'C' RFPs were !
being swapped to troubleshoot RFP and level control instabilities identified during the reactor startup on 12/25/85. During the swapping of B and C pumps, the RFP check valves slamed three or more causing a hydraulic transient in the RFP suction piping. The hydraulic transient resulted in the shearing off of a 1 inch drain line on the 20 inch suction piping to the 'C' RFP, causing a steam and water leak in the i i turbine building. The operators isolated the condensate and feedwater systems, and this action stopped the leak. The RCIC system was +
manually started to control reactor water level. There was no radioactive release from the leak. No personnel contamination ,
occurred. The licensee is inspecting the condensate and feedwater j systems, and initiating repairs. ;
Limerick >
The Philadelphia Electric Company announced on December 23, 1985 that the company's Board of Directors had approved a decision to complete i construction of Limerick Unit 2 under the terms and conditions of the cost containment and operating incentive plans as set forth in the Pennsylvania i Public utility Comission's Order of December 5,1985.
Construction will be resumed as promptly as possible. Construction is projected to be completed by early 1991 at a total cost of approximately
$3.2 billion, including the $894 million expended as of November 30, 1985, at which time the unit was approximately 30% complete. >
Unit I reached the 100% power level,1111 MWe, for the first time on December 26, 1985 and is continuing with its startup testing program.
ENCLOSURE B JM 3 1986 l
4 i
Point Beach Nuclear Plant Unit 2 f 4
On December 27, 1985, a containment inspection was initiated to check t.
on an unidentified decrease in the component cooling water expansion i tank level. At 3:30 p.m., the licensee found a 11 inch crack at the weld point of the component cooling line and the upper oil cooler for Unit 2's "A" reactor coolant ptmp. The leak was approximately four gallons per hour. Unit 2 was taken off line at 3:31 a.m. on December 28, 1985. The weld was grounded out, rewelded and di-penetrant inspected. Unit 2 was back on line at 12:46 a.m. on December 29, 1985. The licensee is investigating the cause of the crack and !
suspects vibration of the component cooling water line as a possible Cause.
! At approximately 4:30 a.m., December 31, 1985, a crack developed in a ;
lightning arrestor insulator in Switchyard Bus, Section 4, for Point '
- Beach Nuclear Plant, Unit 2. A turbine trip and subsequent reactor trip occurred. The licensee declared an unusual event which later was !
cleared at about 6:30 a.m. All safety related systems functioned as required. However, source range instrument N-32 failed and the B :
main steam stop would not shut automatically. The resident inspector 1 and Region III personnel are tracking the event and the licensees repair efforts. .
Rancho Seco I
A meeting with the B&W Regulatory Response Group is scheduled for 1:00 p.m., '
January 8,1986 in Room P-118, Phillips Building, Bethesda, to discuss the December 26, 1985 loss of integrated control system power at Rancho '
Seco. An NRC Incident Investigation Team is at the site. !
[
.I i
i l J
?
I
- ENCLOSURE B i
NRC TMI-2 CLEANUP PROJECT DIRECTORATE WEEKLY STATUS REPORT WEEKS ENDING D,ECEMBER 28, 1985 AND JANUARY 4, 1986
- 1. DEFUELING
- The licensee completed loading one side loading debris bucket with pieces of fuel rods. The bucket containing about 30 lbs. of debris was placed in a fuel canister. Currently two defueling canisters are fully loaded and two are partially loaded.
-- The licensee completed the installation and testing of the debris vacuum system during the week of December 23, 1985. The system uses an air driven submerged pump to pick up a slurry of fuel debris and water. Debris ranging from about 140 microns up .to fuel pellet size are collected in a knockout canister and smaller particles ranging in size down to 0.5 microns are removed from the effluent fluid stream by filter canisters. The knockout and filter canisters serve as the storage and shipping containers for the debris.
- The licensee began vacuum defueling on December 31, 1985. About 300 lbs of debris has been loaded into the knockout canister which has a capacity of about 1,800 lbs. The licensee is working to improve the debris pick up rate of 1 to 2 lbs. per minute that has been achieved so far.
- 2. PLANT STATUS ,
- The facility remains in long term cold shutdown with the Reactor Coolant System (RCS) vented to the reactor building atmosphere and the reactor vessel head and plenum assembly removed from the reactor vessel.
The plenum is on its storage stand in the deep end of the fuel transfer canal. A dam has been installed between the deep and shallow ends of the fuel transfer canal. The deep end is filled with water to a depth of about 20 feet (about 5 feet above the top of the plenum).
- The modified internals indexing fixture is installed on the reactor vessel flange and is flooded to elevation 327 feet 6 inches (151 feet above the top of the core region). The defueling platform is installed over the internals indexing fixture.
Calculated reactor decay heat is less than 12 kilowatts.
RCS cooling is by natural heat loss to the reactor building ambient' atmosphere. Incore thermocouple readings range from 68'F to 95'F with an average of 82*F.
The average reactor building temperature is 60'F. The re3ctor building airborne activity at the Westinghouse platform is 1.1 E-8 uCi/cc Tritium and 1.6 E-10 uCi/cc particulate, predominantly Cesium 137.
l 'd4 0 '996 ENCLOSURE B l
t .
- Spent Fuel Pool "A" is flooded to a depth of 20 feet. About 6 feet of water is over the fuel canister storage racks. -
- 3. WASTE MANAGEMENT
- EPICOR II completed processing Batch 271 which consisted of recirculation of water from CC-T-2 for particulate removal. The total processing volume was about 60,000 gallons. Batch 272 and 273 '
were complete ( for a total of about 15,000 gallons from the SubmergedDemineralizerSystem(SDS)monitortanks.
- SDS is temporarily shutdowr.
- Total volume processed through SDS to date is 3,598,397 gallons, and the total volume processed through EPICOR II is 2,776,536 gallons.
- 4. DOSE REDUCTION / DECONTAMINATION ACTIVITIES
- Decontamination activities are continuing on the 281' level of the auxiliary building. Kelly-vac cleaning of the decay heat vaults is in progress. -
- Average general area radiation dose rate is 40 mrem per hour on the i 347' level of the reactor building and is 67 mrem per hour on the 305' level of the reactor building.
- Decontamination of the "A" D-ring is complete.
- 5. ENVIRONMENTAL MONITORING
- US Environmental Protection Agency (EPA) sample analysis results show TMI site liquid effluents to be in accordance with regulatory limits, NRC requirements, and the City of Lancaster Agreement.
- TMI water samples taken by EPA at the plant discharge to the river consisted of seven daily composite samples taken from December 8 through December 14, 1985 and from December 15 through December 21, 1 1985. A gamma scan detected no reactor related activity.
- The Lancaster water sample taken at the water works intake and analyzed by EPA. consisted of a seven day composited sample taken from December 8 through December 14, 1985 and from December 15 through December 21,1985. A gama scan detected no reactor related radioactivity.
, - Tha NRC outdoor airborne particulate sampler at t,a TMI site ra11Nted a sample between December 18 and December 26, 1985 and bet;aen December 26, 1985 and January 2, 1986. No reactor related radioactntity was detected. Analysis showed Iodine-131 and Cesium-137 concentrations to be less than the lower limits of detectability.
JAN ENCLOSURE B I. '086
- 6. REACTOR BUILDING ACTIVITIES
- Initial vacuum defueling of the reactor core is in progress.
- The pressurizer manway cover has been removed and the access port shielded. Sludge samples have been removed from the pressurizer and further examination is in progress. ,
i 7. AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES
- Installation of the balance of DWCS continued.
- Spent Fuel Pool "A" has been flooded to a depth of about 20 feet (about 6 feet above the top of the fuel canister storage racks).
- 8. NRC EVALUATIONS IN PROGRESS
~
- Technical Specification Change Request number 49.
- Recovery Operations Plan Change number 31.
- SDS Technical Evaluation and System Description Update.
- Core Stratification Sample Safety Evaluation.
- Defueling. Water Cleanup System Technical Evaluation Report, Revision 7.
- Containment Air Control Envelope Technical Evaluation Report, Revision 5.
- Solid Waste Facility Technical Evaluation Report.
- 9. PUBLIC MEETINGS The next meeting of the Advisory Panel is scheduled for February 12, 1986 at the Holiday Inn, 23 South Second Street, Harrisburg, PA from 7:00 PM to 10:00 PM.
, Persons desiring the opportunity to speak before the panel are asked to contact Mr. Thomas Smithgall at 717-291-1042 or write to him at 2122 Marietta Avenue, Lancaster, Pennsylvania 17603.
i l
i l
JAN 3'93o ENCLOSURE B
_-._---_----------_----,---------,--------._-s.--.----------------------_.--.--_------._,--_-------____.--_--u-----..---._---,--,.m +--_s-
. . . . . - - - - - -. . - _ _ . _ . _ - - .- .. .. -=
J
- t 9
i 4
0FFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS '
i
] Items of Interest. ;
Week Ending January 3, 1986 4
{ Near-Tern NRC Actions Hnder the Nuclear Waste Policy Act (WPA)
Section: 137 of WPA: Transportation of HLW 1 Status: DOE issued the draft Transportation Institutional Plan in September
{ 1985, with ccaments due to DOE by December 31, 1985.
! Action: NRC staff expects to transmit formal comments to DOE shortly. DOE
, expects to issue the Final Transportation Institutional Plan by May i
1986.
Section: 141(b) of NWPA: Submittal of MRS Proposal l t
i' Status: DOE submitted to the Commission the Monitored Retrievable Storage facility proposal on December 24, 1985.
- Action: NRC has 45 days to review the proposal and transmit comments to
, 00E. Staff is currently preparing comments for Commission review
] and approval. NRC comments will be submitted with the proposal to j Congress in early February 1986.
Section: 141(d) of NWPA: Licensing of MRS
- Status: NRC has developed revisions to 10 CFR Part 72 to provide the !
licensing framework for the MRS, should it be authorized by Congress. !
Action: The proposed rule on 10 CFR Part 72 was submitted to the Commission (SECY-85-374) on November 25, 1985 for approval, which is expected in January 1986.
}
4 Section: 306 of WPA: Regulations for Training of Power Plant Personnel.
j Status: The final rulemaking package on Part 55 dealing with simulator i i training requirements and three associated regulatory guides is
- undergoing final Office review. The full ACRS approved the' rulemaking package at their 308th meeting on December 5-7, 1985.
Action: The final rule will be submitted to CRGR for review-in February l 1986, and then to the Commission for approval.
+
i i
! i ENCLOSURE C JAN 3 1986
_. ~ _ . _ . _ . _ . _ . _ . _ _ . . . . _ . _ . . _ . _ _ _ _ _ _ _ . _ _ . _ _ _ . . _ , - _ . , - , , _ . _ , . _ _ _ , _ . _ , _ , _ , . - .
i 4
[
2- \
Section: 121(a) of NWPA: EPA Final High-Level Waste Standards ;
I :
Status: EPA final : rule for Environmental: Standards for the Management and l Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Waste became effective November 18, 1985 (50 FR 4003). ;
} . Action ~: Staff is currently preparing revisions to 10 CFR Part 60 for I i conformance to EPA standards, and will submit a proposed rule to the i Commission, currently scheduled for_ February 14, 1986.
l Section: 114(a)(2)(A) of NWPA: Second Repository Status:* DOE plans to issue a draft Area Recommendation Report (ARR) on j i January 16; 1986. This report identifies 15-16 sites as possible i
{ locations for the second repository. j
} Action: NRCwillNommentonthereportwhenitisreleased.
Section: 113(b)(1) of NWPA: Waste' Package / Form Description i
( ;
- Status
- Before sinking shafts, DOE is to issue a description of the possible [
form or packaging for HLW of SNF. This will be issued with the SCP i
- for each candidate repository site. l
! Action: DOE and NRC will be' conducting a joint Salt Waste Package Workshop '
l' on January 22-24, 1986 in Columbus, Ohio, to discuss waste package l design and licensing under 10 CFR Part 60. j r
10 CFR 73.71 - Reporting Requirements for Safeguards Events ,
g "
The public comment period for 73.71, Safeguards Reporting Requirements closed
! on Tuesday, December 31, 1985. In general, comments have been supportive of
- the intent and substance of the rule. Several commentors have questioned the i need for a "24-hour" log and subsequent quarterly submittal. During the
1 analysis of public comment we will reexamine this requirement and see if_there l are alternative means of acquiring information on equipment and/or personnel l; failures in ' order to perform generic analyses. , .
j t
) NFS-Erwin a -
' q' i . t l As of January 2,1986, the LCor Strike at NFS/Erwin is continuing. No date [
l has been set for further negotiation. t l
An Enforcement Conference concerning the recent' incident of a handgun having !
been taken into the NFS/Erwin protected area is scheduled for Tuesday, l January 7,.1986 at Region II. A Safeguards representative will attend. ;
- v l y 31986 ENCLOSURE C l
! i
, +
'( +,- f a, - --.-..--t.-_-----.-.--
3_
RER Schedule At the request of the licensee we have postponed the Diablo Canyon RER originally scheduled for January 13th. It has been rescheduled for May 1986.
The next RER site visit is scheduled for February 3rd (Farley 1 and 2, Alabama).
a t
e i
4 i
i f
a I
i l
.i 4
.l I
i i
f i
4 31986 ENCLOSURE C 4
JAN
-- - , --,m. _ , , - - . . .- . ._ - - - . - - ,- - . - , . _ , - , - - . . .
o m
Office of Inspection and Enforec.ment
- l Items of Interest Week Ending January 3,1986 v ,
- 1. The following Significant Enforcement Actions were tal;en"during the past week: ,
None.
- 2. The following IE Preliminary Notifications were issued during the past week:
- a. PNS-I-86-01, Public Service Electric & Gas Company (Hope Creek NuclearGenerating-Station),BombThreat.
- b. PNO-II-85-120, Georgia Power Compary (Votgle Unit 1), Media Inter'est in Containment Evacuation. -
- c. .PNO-II-85-122, Virginia Electric & Power Company (North Anna Unit 1),
Shutdown in Excess of 48 Hours.
- d. PN0-II-85-123, Duke Power Company (Catawba Unit 1), Introduction of Weapon.Into Plant's Protected Area.
W None. ,
- 4. Other Items
- a. FEMA Report FEMA provided a report on the July 16, 1985 exercise at Davis-Besse and informed staff of notification made to the State of Ohio authorities in emergency plan issues that require state response.
i a N b ?
s
- t i
g g4
^
ENCLOSURE D JAN 31986 ,
b
OFFIC'E OF NUCLEAR REGULATORY RESEARCH Items of Interest -
Week Ending January 3,1986 NRC Staff Participation in Utility Workers Union Nuclear Safety Conference Members of the NRC staff recently made presentations at the Utility Workers Nuclear Safety Conference, held in Washington, DC, by the Utiiity Workers Union of America. The topics covered were: major revision of 10 CFR Part 20 (R. E. Alexander, RES); legal status of NRC technical specifications, orders, guides, generic letters, NUREG reports, policy statements, etc.
(Stephen G. Burns, ELD); new recertification and licensing regulations for reactor operators (Susan F. Shankman, NRR); recent developments in plant security regulations (George W. McCorkle, NMSS). During the 4-hour meeting the workers were frank and outspoken about several of their concerns which involve the NRC:
(1) some utilities, claiming that NRC policy statements are binding,,are using the statement to justify positions inimical to union interests; (2) in requests for changes to their technical specifications, utilities often include nonessential commitments inimical to union interests; (3) many union members feel that NRC provisions for public input are not working--that workers are often left out of the decision-making process; "(4) nuclear power plant workers believe that there is a potential for unfair treatment of union workers vis a vis management personnel unless all elements of the Access Authorization Program are applied consistently and in an even handed manner"; (5) some NRC resident inspectors do not report non-radiation hazards to OSHA, as specified by.NRC procedures; (6) certain drug-testing aspects of the fitness-for-duty programs under consideration are infringements of constitutional rights and will be fought by the unions. The attendees did not raise questions about the proposed major revision of 10 CFR Part 20.
James Joy, UWUA President, stated after the session that the contributions of l the NRC representatives every year are the most valuable presentations of their conference.
I i
l l
l JAN 31986 ENCLOSURE E
~
~
. FRN on Part 20 to be Republished Due to Typesetting Errors On December 20, 1985, the NRC published in the Federal Register a notice of proposed rulemaking for 'a major revision of 10 CFR Part 20, " Standards for Protection Against Padiation." The 120-day comment period was scheduled to close April 21, 1986. However, when it became apparent that an unusually large number of typesetting errors had been made in the notice, it was decided to reprint the entire notice (at GPO expense). The notice is scheduled for republication on January 10, 1986, and the comment period is being extended to May 12, 1986, accordingly. NRC distribution of copies of the notice to licensees and other known interested parties is being delayed so as to permit using the corrected, reprinted notice.
4
~
RES Rulemaking Activities Emergency Preparedness for-Fuel Cycle and Other Radioactive Materials Licensees
[ Parts 30,40,70)
Ir.1981 the NRC issued orders to certain fuel cycle and other radioactive material licensees requiring them to submit comprehensive onsite radiological emergency plans. Rulemaking was initiated on August 3,1981, for codification of those orders.
CRGR considered the rule on November 27, 1985, and voted in favor of rulemaking by a vote of 4 to 3. liowever, the minutes of the meeting are expected to indicate that everyone agreed that the rule is not justified technically (by a criterion such as $1000/ man-rem) but is favored because of policy issues.
Severe Accident Risk Assessment The RES staff and supporting contractors are currently engaged in the reevalua-tion of the risk of six reference LWRs. This reevaluation is currently being used to support NRR's review of IDCOR submittals. In addition, it will support a the staff report NUREG-1150, which is intended to provide guidance to decision-makers as to the appropriate role of information on core melt frequency, containment performance, source terms, and risk in making severe accident decisions.
Discussions have been ongoing between NRR and RES to develop a more fully integrated approach for establishing reasonable ranges and degrees of belief for the major risk uncertainties in the NUREG-1150 reference plant analyses.
The outcome of these discussions likely will be that NRR will pick up responsibility for three more of the issue papers (core-concrete, direct heating, and hydrogen production); and teams will be established for each issue consisting of representatives from RES, NRR, and contractors. A series of checks and balances will be established to assure that all available technical information will be reasonably displayed and that the views of all team members will be heard; and the mechanism for review and approval of the resulting position papers will include the cognizant RES and NRR branch chiefs and division directors, as well as the SARP Senior Review Group. This process not only should improve the quality of and the NRC consensus on these position papers, but it should also enhance consistency between NUREG-1150, the revised NUREG-0956, and the supplement to NUREG-0900.
4 ENCLOSURE E JAN 31986
. , 4J ' ; )
Shipping Cask Response to Severe Transportation Accidents--Modal Study 4
The purpose of this study is to determine the performance of licensed casks under various types of realistic accidents that might occur during shipments of spent fuel. This purpose is being accomplished by assessing the performance when subjected to severe transportation accident environments, as well as by assessing .the likely frequency of such environments. A final report was scheduled to be completed by mid-December.
A meeting was held on December 18-19, 1985, at LLNL to discuss NRC comments on draft sections of the Engineering Report on the above subject. Recommended outlines for two sections were developed and given to LLNL for their consideration. Agreement was reached that a third section discussing potential radiological effects resulting from transportation accidents would be rewritten since the presentation was based on a misinterpretation of a referenced NRC document. Significant work still needs to be completed within the constraints of the remaining half of the allocated funding. The latest schedule indicates completion of the draft final report in mid-February--a 2-month slippage from the original schedule. A trip report on the meeting has been prepared.
ENCLOSURE E JAN 3 1986
ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING JANUARY 3, 1986 Sicnature of NRC-STA- ANRE/MITI Arrangement On December 31, 1985 William J. Dircks, Executive Director for Operations, signed for the NRC the renewal texts (both English and Japanese languages) of the " Technical Exchange Arrangement Between the U.S.N.R.C., the Science and Technology Agency of Japan (S.T.A.) and the Agency of Natural Resources and Energy of Japan (A.N.R.E.) in the Field of Nuclear Regulatory Matters and Nuclear Safety Research." The Japanese parties had signed on December 28, 1985. The Arrangement has a duration of five years.
New Swedi_sh Requirements to Improve Protection Against Releases from Severe Reactor Accidents Based on reviews of plant-specific severe accident studies by the owners of the nuclear power plants at Forsmark, Oskarshamn and Ringhals, the Swedish Nuclear Power Inspectorate (SKI) and the National Radiation Protection Institute (SSI) have proposed new requirements with respect to improving protection against large releases. A government decision on the proposed reouirements is expected early in 1986 and, if approved, would be required to be implemented by September 1,1989 at the latest.
A three-page telex describing the proposal is available in IP (R. Hauber, x-27131). Highlights of these new requirements include:
- improved protection of containment penetrations and support structures.
- rapid flooding of lower dry-wells of certain BWRs.
E installation of pressure relief devices, to protect against containment overpressure events, which can function independently of operator action and other safety systems and which also can be used by operators for monitoring radioactivity releases and for accident management actions. These devices and other safety systems (e.g., containment sprays) should ensure with high reliability that releases to the environment are kept below 0.1 percent of the inventory in a 1800 MW (thermal) core, excluding noble gases. (These guidelines put a high priority on prevention of extensive ground contamination in order to limit social consequences and also provide a good margin against acute radiation illnessandfatalities.)
- the release protection level is eaual to that required for the Barseback plant with its Filtra filtered vent system. Alternative technical solutions are presently being discussed with the owners of the Forsmark, Oskarshamn and Ringhals plants: large area, JAN 3 1986 ENCLOSURE G
. 2 New Swedish Requirements to Improve Protection Against Releases from Severe Reactor Accidents continued unfiltered and reclosing relief systems to cope with drywell to wetwell isolation failure in combination with a LOCA in BWR pressure suppression containments; improved containment spray systems; and small area venting with scrubbers or filters to provide long-term pressure control in the containment.
Foreign Trip Reports Themis P. Speis, Director, DST September 30-October 4,1985; Visited France:
The purpose of the trip was to conduct technical discussions with the Institute for Nuclear Protection and Safety (IPSN) of the French Atomic Energy Commission (CEA) and Electricite de France (EdF) on the French Paluel nuclear power plant design. NRR is conducting a review of design differences between the French P41300 MWe standard plant (Paluel) and a typical current U.S. PWR in order to evaluate the safety significance of these design differences. (This report is Proprietary.)
G. Ted Ankrum, Chief, 0AB/IE October 3-4, 1985; Visited the FRG:
The purpose of the trip was to discuss final arrangements for NRC to reply on the Bundesanstalt fur Material Prufung (BAM) and the Technischer Ueberwachungs-Verein in Berlin (TUV-Berlin) as an agent for inspection of dry storage casks produced in the FRG.
James R. Shea, Director, IP October 14-18, l'985; Visited Spain:
Mr. Shea participated in the Third International Conference on Nuclear Technology Transfer held in Madrid where he presented a paper on NRC activities in international safety cooperation.
ENCLOSURE G JAN 31986
OFFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA Items of Interest Week Ending January 3,1986 AE0D issued Case Study report AE0D/C504, entitled " Loss of Safety System Function Events." The study identified 133 events involving a loss of safety system function (LSSF) in the 1981 to June 1984 time period, 87 of which (65%)
were the result of human factors contributions.
Although the study found no evidence of any previously unrecognized safety problems, it did find that over the time period considered in the study there is no clear evidence of improvement in preventing loss of safety system events. Therefore, the report contains recommendations that are intended to increase awareness of the causes and contributing factors of this type of event. The recommendations have been forwarded to IE and NRR for their review and appropriate action.
i l
i l
l I
i JAN 31986 ENCLOSURE J
- ITEMS ADDRESSED BY THE COMISSION - WEEK ENDING JANUARY 3, 1986 A. STAFF REQUIREMENTS - BRIEFING ON NUCLEAR EMPLOYEE DATA SYSTEM (NEDS),
4 2:00 P.M., TUESDAY, DECEMBER 17, 1985 COMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to RECORD dated 12/30/85 The Commission met with utility representatives to discuss development of the Nuclear Employee Data System (NEDS) . The -
following persons participated-in this briefing:
Peter Moeller, Chairman NEDS Steering Committee and
, Manager of Site Protection Public Service Electric and Gas -
John Baylish, Chairman NEDS Security Subcommittee and '
Chief, Nuclear Sita Protection Public Service Electric and Gas Wayne.Britz, Chairman NEDS Health Physics Subcommittee and Manager, Radiation Protection Public Service Electric and Gas
- i Dick Sutton NEDS Program Manager International Energy Associates ,
l There were no requirements at this meeting.
B. STAFF REQUIREMENTS MEMORANDUM - AFFIRMATION / DISCUSSION AND VOTE, 11:30 A.M.,
WEDNESDAY, DECEMBER 18, 1985, COMMISSIONERS' CONFERENCE ROOM, D.C. 0FFICE-(OPEN TO PUBLIC ATTENDANCE) MEMO SECY to H. H. E. Plaine dated 1/2/86 I. SECY-85-241A -
NOTICE OF HEARING ON TMI-2 LEAK RATE DATA FALSIFICATION The Commission (with Chairman Palladino and Commissidners Roberts and Zech agreeing) approved an order, establishing a three member Board to preside over a hearing to develop the facts surrounding the reactor coolant system leak rate data falsifications at TMI Unit 2 prior to the March 28, 1979 accident in-sufficient detail to determine the ultimate status of those likely involved, including those segregated from TMI-l and those now working at other facilities. The hearing will be of the legislative format designed solely to gather l information and issue a recommended decision setting forth the !
facts, in order for the Commission to determine what action, '
if any, will be taken. ]
ENCLOSURE O JAN 31986 ;
2 B. CONTINUED Commissioners Asselstine and Bernthal disapproved the order and provided separate views. - -
(Subsequently, on December 18,'1985, the Secretary signed the l Order.)
II. SECY-85-391 -
PETITION FOR REVIEW OF APPEAL BOARD
- DECISION ON SHOREHAM EMERGENCY PLANNING / LEGAL AUTHORITY ISSUES (ALAB-818) i The Commission 2 (with Commissioners Roberts, Bernthal, and Zech agreeing) approved an order that indicates that the :
Commission is taking review of AL4B-818 but defers briefing l and decision until the Appeal Board has reviewed all currently i pending emergency planning issues. Chairman Palladino and l t
commissioner Asselstine disagreed and would have taken review j and decided the preemption issues as soon as possible. Both !
provided separate views.
l (subsequently, on December 19, 1985 the Secretary signed the l Order.) , l i
1/ !
Section 201 of the Energy Reorganization Act, 42 USC S 5841, !
provides that action of the Commission shall be determined by !
a " majority vote of the members present." Commissioner !
Bernthal was not present when this item was affirmed. !
Accordingly, the formal vote of the Commission was 3-1 in l favor of the decision. Commissioner Bernthal, however, had !
previously indicated that he would disapprove this paper and f had he been present he would have affirmed his prior vote. l
' ~
2/ f Section 201 of the Energy Reorganization Act, 42 USC S 5841, I l
provides that action of the Commission shall be determined by (
a " majority of the members present." Commissioner Bernthal I was not present when this item was affirmed. In order to I allow the will of the majority to prevail Commissioner !
Asselstine did not participate in the formal affirmation on this issue. Accordingly, the formal vote of the Commission L was 2-1 in favor of the decision. Commissioner Bernthal, !
however, had previously indicated that he would approve this f issue and had he been present he would have affirmed his prior {
vote. Commissioner Asselstine had previously indicated his !
l disapproval and he wculd have affirmed his vote.
[
f ENCLOSURE O +
JAN 3 1986 i l 5
._.__-..__._,___,.[
se NMSS MEETING NOTICES FOR WEEK ENDING: 1/3/86
Division of Fuel Cycle and Material Safety 5
o DOCKET ATTENDEES /
DATE/ TIME NUPSER LOCATION PURPOSE APPLICANT NRC CONTACT s-1/10/86 Willste To discuss transportation matters L. Barrett, Cook 9:30 am Room 562 related to future shipments under B. Philpott (DOE) the NWPA. W. Chu, R. Hannan (DOT)
R. E. Cunningham (FC)
J. Cook (FC)
C. MacDonald (FC) 1/15/86 Willste Meet with Waste Management Group R. Odegaarden (FC) Odegaarden 9:00-12:00 5th floor (WMG) to discuss proposed irrsdiated H. Lee (FC) ~
conf room HDWR package - French design. C. MacDonald (FC) i P. Tuite (WMG)
- Division of WP:te Pianagement
) None Division of Safeguards None 4
6
- h n
=
, - -, , - - - - , , - - - . . , - - - . . . , . . - . - .-,. ~,. ..- . . . . . . . _, - . ~~
i; z
RES MEETING NOTICES January 3,1986 bs s DOCKET APPLICANT /
PURPOSE ATTENDEES NRC CONTACT-DATE/ TIME' NUMBER LOCATION New Orleans Attend ASTM C-26 Nuclear Fuel Cycle Frattali.
1/12-17/86 Mee tings -
ERAB Civilian Nuclear Power Plant Mtg. ~Minogue >
1/23/86- DOE Forrestal 9:00-5:00 Bldg. of Subpanel on LWR Utilization '
Room.4A-110 ,
Carnegie Conf. Committee on Interagency Radiation Minogue-1/23/86 Research and Policy Coordination -
1 :30-4:00 Center 11 DuPont Policy Panel Meeting Circle I
n liim T
i
- e
1 J;nuary 3,1986 ,
t
- $ 3 3:n RI t eqEETIIIG IIOT f CE 2 .
XI DOCMET ATTENDEES /
PUR POK APM ICAall flRC C0ff1ACT DATE/TWEE E J3 N LOCATloss Ril Ofrece NFS Enforcement Conference Licensee, Deputy Olshinski
'D 01/0T/26 Regional Administrator
-i 10:30 sm and selected Rt1 Staff
{ Ptembers 7
-4 FPet Enforcement Conference Same as above Croce
-D 01/08/f6 R34 Office 1:00 pe Turkey Point Facility Charlotte, IOC Duke Power Company - Catewtpa Same as above Olshinski
, 01/10/16 SALP Presentation 10:00 se
'O
~ ,
I
-O
-(D
.N (D
01 I ..
7
' CJ 4
! .T i
-4
-O I-4
- D
. F T
P Pn .
c:
o l
. . . -