ML20211K265
| ML20211K265 | |
| Person / Time | |
|---|---|
| Issue date: | 06/26/1986 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-860620, NUDOCS 8606270359 | |
| Download: ML20211K265 (34) | |
Text
'k(NY s
1 June 26, 1986 For:
The Commissioners From:
T. A. Rehm, Assistant for Operations, Office of the ED0
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING JUNE 20, 1986 A summary 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*
Resource Management I*
Analysis and Evaluation of Operational Data J
Small & Disadvantaged Business Utilization & Civil Rights K*
Regional Offices L*
CRGR Monthly Reports M
Exec'utive 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 wJ T. A. Rehm, Assistant for Operations Office of the Executive Director for Operations
Contact:
T. A. Rehm, ED0 492-7781 8606270359 860626 PDR COMMS NRCC WEEKLYINFOREPT PDR
HIGHLIGHTS OF WEEKLY INFORMATION REPORT
.c WEEK ENDING JUNE 20, 1986
.Earthouake Felt at Oconee Nuclear Station. Units Nos.1. 2 and 3 On June 11,1986 at 12:12 p.m., an earthquake was felt at the Oconee Nuclear Station, Units 1, 2 and 3 and its magnitude was estimated at 2.8 on the Richter scale. An aftershock was felt about 10 minutes later with a magnitude of about 1.5.
The earthquake did not damage the nuclear units, set-off any alams, or trigger any of the strong motion instruments. However, the operators state that it was felt in the control room.
A previous earthquake was felt on February 13.-1986 with a magnitude of 3.5.
The units did not trip and continued on operate.
Seouoyah Fuels Corooration During the week of June 9, 1986, Region IV conducted a closeout inspection of i
Kerr-McGee's Sequoyah Fuels UF, production facility in Gore, Oklahoma. NHSS staff participated in this eff5rt. in order to review the status of plant safety modifications, procedures, training, commitments, recommendations, and contin-gency planning related to startup of UF, production. During the exit briefing held June 12, 1986, several of the appr5ximately 30 open items generated from the January 1986 inspection were closed out, however, many remain.
In addition, procedures and training commitments remain to be completed and the dedicated safety and emergency equipment have not yet been received. An earlier test of the contingency plan's public notification system indicated problems which remain to be resolved.
Distribution of Radioactive Toca: Gems -
It recently came to the attention of 1915S that at least one research reactor is irradiating gemstones and distributing them with induced radioactivity.
Other reactors have called and expressed interest in the same activity. A t
part 32 license is requir:d to distribute radioactive consumer products, and no reactor possesses such a license. 19155 has never issued a license authort-zing the distribution of radioactive gens, because of the Commission policy against allowing distribution of radioactive toys, novelties, or adornments.
I Region III inspection staff is taking appropriate enforcement action with respect to the research reactor that we know is distributing radioactive gens.
They are also asking the other Regions to check other reactors. NRR is pre-paring a generic letter to all research reactors reminding them of NRC require-ments on distribution of radioactive products to unlicensed persons.
The staff is further evaluating whether DOE reactors and/or imported gems may b4e involved, and whether it may be permissible to hold irradiated gems until the radioactivity decays away.
Severe Accident Risk Assessment The RTS staff and supporting contractors are currently engaged in the reevalua-tion uf 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 the s'aff 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.
i Work (.ontinues on the development of technical position papers for the principal parameters affecting the risk estimates. While consensus is being reached on a number of these issues, some (such as direct heating) are not resobed at present. It is hoped that all issues will be resolved within the next faw weeks, but it is not clear at present whether there will be substantial differences between the staff's positions and the contractor's. If there are substantial differences that must be analyzed for NUREG-1150, it is likely that this would threaten the September 30 publication date for the draft.
JUNE 20, 1936
o 0FFICE OF ADMINISTRATION Week Ending June 20, 1986 ADMINISTRATION OF THE FREEDOM 0F INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Carryovers,1985 181 15 Raceived, 1986 456 94 Granted 299 28 Denied 77 13 Pending 261 68 ACTIONS THIS WEEK Received (Anindividual Requests records maintained by the NRC on himself.
requesting information about himself)
(86-436)
Peter C. Hearn, Requests a copy of the memo concurred on by persons in NTEU Steward NRR who contributed to the composition of the position (86-437) description for Vacancy Announcement No. 86-0716-5.
Paul D. Eddy, Requests copies of 01 Reports 1-85-020 and 1-86-010 State of New York on the Nine Mile Point nuclear power plant.
Department of Public Service (86-438)
Howard L. Vener, Requests a copy of the license application for South Stone & Webster Jersey Processing Technology, Inc.
En ineering Corp.86-439)
Mark C. Johnson, Requests a copy of the purchase order awarded to 3M Panafax Corp.
regarding Region III's lease / purchase of 3M facsimile (86-440) equipment.
Jim Hoyt, Requests a copy of contract number NRC-33-86-276.
Data General (86-441)
CONTACT: Donnie H. Grimsley 492-7211 JUNE 20, 1986 ENCLOSURE A
2 o
Received, Cont'd (NRCemployee)
Requests records in the personnel security file en her.
(86-442)
A.N. Tschaeche Requests records pertaining to Docket 20-16 cr the (86-443)
Comission's decision to deny the petition for rulemaking.
(An individual Requests a copy of the transcript of his interview with the NRC regarding the Nine Mile Point nuclear requesting )
power plant.
information (86-444)
Lynn Connor, Requests printouts, with interpretive keys, of the Doc-Search computerized steam generator Status infortitation.
Associates (86-445)
(NRCemployee)
Requests four categories of records.
(86-446)
Pat Costner, Requests copies of " Materials Unaccounted for" reports National Water for the Sequoyah Fuels Corporation facility from initial Center startup to the present and reports related to specified (86-447) matters at the Fernald Uranium Processing facility.
Sandra Vasa-Sideris, Requests copies of results sumary sheets for the periods Georgia State from January 1983 through December 1964 for specified University plants.
(86-448)
James B. Hamlin, Referral from the D0J of one record regarding the South Shaw, Pittman, Texas nuclear power plant.
Potts & Trowbridge (86-449)
(NRCemployee)
Requests a copy of a specified 01A investigation report.
(86-450)
Billie P. Garde, Requests copies of all records related to overview, Government regulation, and investigation of the receipt of 93%
Accountability enriched uranium at the Comanche Peak nuclear power plant.
Project (86-451)
Billie P. Garde, Requests copies of records related to Inspection Report Government 85-10/85-15 on the Comanche Peak nuclear power plant.
Accountability Project i
(86-452)
Billie P. Garde, Requests copies of records regarding Enforcement Action Government EA 86-36/86-09 regarding the Comanche Peak nuclear power Accountability plant.
Project (86-453)
JUNE 20, 1986 ENCLOSURE A
O 3
Received. Cont'd Billie P. Garde, Requests copies of all records related to the NRC's Government review of ISAP's I.a.4, I.b.3, II.b., III.d., and l
Accountability VII.b.2., released by Texas Utilities on April 14, Project 1986.
(86-454)
Jim Pedro, Requests copies of the March 3, 1986, and Aug'ust 13, 1985, NUS Corporation memoranda by T. Speis regarding the CRGR package for j
(86-455) proposed resolution of USI A-17.
(Anindividual Requests copies of 01 Investigation Report 1-84-014 i
concerning the Nine Mile Point nuclear power plant and
. requesting )
a copy of his interview with the NRC.
information (86-456) j Harry H. Voigt.
APPEAL TO THE COMMISSION for the lack of response to a LeBoeuf, Lamb, request for three specified records regarding TMI.
Leiby & MacRae (86-A-93-86-369) i Billie P. Garde, APPEAL TO THE EDO for the release of the withheld portions i
Government of four denied records regarding the EG&G report on the Accountability Comanche Peak nuclear power plant with regard to Project harassment and intimidation.
(86-A-94-86-223)
Grante.d Marjorie M. Aamodt In response to a request for correspondence between named I
l (86-185) persons subsequent to R. DeYoung's October 3,1979, memo l
on the subject of off-site iodine-131 air concentrations, made available seven records.
Informed the requester that i
additional records subject to this request are already available at the PDR.
4 G. Koumal, In response to a request for copies of coments on Engineering establishing a Federally Funded Research and Development Technology Center for Waste Management Technical Assistance, 2
i International USA informed the requester that these records are already l
(86-365) available at the PDR.
4 Robert W. Laza, In response to a request for all annual reports prepared Theodore Barry by Region III presenting comparative data for operating
& Associates and construction plants, made available five records.
(86-388)
Informed the requester that one additional record subject to this request is already available at the PDR.
1 Ronald A. Rose, In response to a request for copies of the latest 1
F0I Services, Inc. radiological inspection reports for seven specified-l (86-390)
Ethicon(J8J) facilities,madeavailablefourrecords.
l Informed the requester that Georgia, New Mexico, Texas, and North Carolina are Agreement States and that he may contact Stat.e officials for records.
i i
JUNE 20, 1986 ENCLOSURE A
~.
_ _ _ -.. _ _ ~ -. _.. _. _., _ _ _ _ - _. _ _. ~
~_
4 Granted, Cont'd Ronald A. Rose, In response to a request for copies of inspection reports FOI Services, Inc. for the past five years and pertinent correspondence (86-397) relating to license 20-00277-03 issued to Tech / Ops Inc.,
Burlington, Massachusetts, made available 21 records.
4 Informed the requester that additional records subject to this request are already available at the PDR'.
Andrew Hodgdon In response to a request for copies of all correspondence (86-403) between Harvard and NRC related in Region I's inspection at Harvard University in 1986, made available eight records.
Philip J. Imbrogno, In response to a request for copies of all records Windward School, regarding sighting of a UFO at the Indian Point White Plains, plant on July 24, 1984, and from January 1983 to May 1986, New York informed the requester that the NRC has no records subject (86-422) to this request.
Mark C. Johnson, In response to a request for a copy of the purchase order Panafax Corp.
awarded to 3M regarding Region III's lease / purchase of 3M (86-440) facsimile equipment, made available one record.
Denied Stevi Stephens, In response to a request for records within the Office of 8
Nuclear Awareness investigations' (01) case files regarding investigations Network which have occurred within the time frame May 1, 1985, and (85-600)
August 27, 1985, made available three records. Denied in their entirety the records contained in four 01 case files l
and portions of four records, release of which would j
interfere with an ongoing enforcement proceeding. Denied i
portions of two records, disclosure of which would constitute a clearly unwarranted invasion of personal privacy.
(NRCemployee)
In response to a request for copies of an OIA investigation (86-349) report and related records, denied the records in their entirety containing investigatory material compiled for an ongoing investigation.
(NRCemployee)
In response to a request for records regarding an 01A (86-357) investigation, made available one record. Denied two i
records in their entirety, release of which would interfere with an ongoing investigation.
a Kathiann M. Kowalski, In response to an APPEAL TO THE EDO for the release of Squire, Sanders two denied records regarding Amax, Inc.'s Parkersburg l
& Dempsey site, made available one record. Denied portions of one (85-A-41-85-375) record containing information about the Naval Nuclear Propulsion program that has been classified as Restricted i
Data.
JUNE 20,1986 ENC 1.0SURE A
1 WEEKLY INFORMATION REPORT i
DIVISION OF CONTRACTS WEEK ENDING JUNE 20, 1986 RFP ISSUED k
RFP No.: RS-RG4-86-329
Title:
" Data Entry Support Services for Region IV"
==
Description:==
Effort involves data entry, editing and reporting activities relating to various systems for which NRC's Region IV office is responsible.
Period of Performance:
24 months Sponsor: Region IV i
Status: RFP issued on June 18, 1986. Proposals due on July 17, 1986.
RFP No.: RS-ORM-86-281
Title:
" Comprehensive Current (Real-Time) Geophysical Data Storage and Retrieval System"
==
Description:==
The system must be able to retrieve, display and sumarize geophysical information for user specified areas located anywhere within the United States. This information is needed in the form of a data base depicting the applicable reporting station, forecasted conditions for specified areas and severe advisories or reports.
4 Period of Performance: One year with two one-year options.
Sponsor: Office of Resource Management Status: RFP issued on June 16, 1986. Proposals due July 14, 1986.
l PROPOSALS UNDER EVALUATION RFP No.: RS-ORM-86-261
+
Title:
" Engineering Cost Analyses of Proposed Changes in NRC Requirements"
==
Description:==
Services for engineering cost analyses to identify, derive and analyze the engineering costs of proposed changes in NRC regulatory requirements.
i Period of Performance:
30 months i
Sponsor: Office of Resource Management i
Status: RFP closed on June 17, 1986. Proposals forwarded to Source Evaluators j
for review on June 18, 1986. Competitive range to be established on j
July 3, 1986.
l l
RFP No.: RS-0RM-86-264 l
Title:
" Development of the Corporate Data Network"
==
Description:==
The contractor will develop shared data bases utilizing the Data Base l
Management System package IDMS/R and strategic data planning and i
information engineering methodologies.
i Period of Performance: Three years Sponsor: Office of Resource Management i
Status: The competitive range has been established and negotiations are scheduled i
for the week of July 7, 1986.
i l
ADMINISTRATIVE MATTER l
As reported in the Weekly Information Report for the week ending June 13, 1986, SMC O'Donnell and Associates, Inc., (SMC O'Donnell) filed a protest with the r
Contracting Officer on June 5, 1986, under Solicitation No. RS-0IE-86-155 for
" Technical Assistance for Design Inspection Services." Based on a review of the protest, the protester's proposal and other relevant facts, the Contracting Officer j
found that the proposal was properly excluded from the competitive range for the effort. By letter dated June 19, 1986, the protest was denied.
JUNE 20, 1986 ENCLOSURE A
l OFFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending June 20, 1986 Pilgrim Nuclear Power Station
]OnJune 12, 1986, union members at the Boston Edison Company voted in favor of a new contract and concluded the strike which began on May 15, 1986.
Pilgrim Station is expected to restart about mid-July following completion of work on hardware and programmatic issues.
Comanche Peak In a memorandum and order issued on June 12, 1986, the ASLB ordered intervenor CASE to file a proposed litigation plan for the hearing. The Board stated that, since CASE has twice prevailed, fairness dictates that CASE should be j
given the opportunity to propose a workable schedule that will give it control over the presentation of its case.
The Board asked that the schedule provide for the completion of all hearings by the end of July 1987, and suggested that it should be possible to begin hearings on some subjects by early August 1986. The Board also encouraged CASE, in preparing its schedule, to be specific about what issues or portions of issues will be tried.
Catawba Unit 1 At about 3:45 p.m. on June 13, 1986, Catawba Unit 1 encountered a 25 GPM leak through a socket weld crack on the RCS letdown line for about 40 minutes before it was isolated. The crack in the socket weld appears to have been accelerated by a transient that caused the variable orifice letdown valve to flop open. Radiation levels did not increase inside containment.
The licensee has cut-out a section of the piping and sent it to Westinghouse 4
to investigate the failure mode, and will investigate to find if other socket welds at the facility are affected.
The staff is following up the licensee's efforts to determine the root cause of the weld failure, j
Earthquake Felt at Oconee Nuclear Station Units Nos.1. 2 and 3 On June 11, 1986 at 12:12 p.m., an earthquake was felt at the Oconee Nuclear Station, Units 1, 2 and 3 and its magnitude was estimated at 2.8 on the Richter scale. An aftershock was felt about 10 minutes later with a magnitude of about 1.5.
The earthquake did not damage the nuclear units, set-off any l
l alarms, or trigger any of the strong motion instruments. However, the operators l
state that it was felt in the control room.
l A previous earthquake was felt on February 13, 1986 with a magnitude of 3.5.
I The units did not trip and continued to operate.
3 i
.l JUNE 20, 1986 ENCLOSURE B
i'.
River Bend Station I
At 3:55 a.m. (CDT) on. June 14, 1986, River Bend Station experienced an unplanned reactor trip from 76% of rated power. The licensee was in the process of conducting a weekly test of turbine stop and turbine control valves.
During the test, the turbine tripped on high vibration. The turbine trip, in turn, caused the reactor trip.
During the scram, three other events occurred:
(1) Two SRVs momentarily lifted due to high pressure; (2) The "B" recirculation pump did not operate as expected in that the low speed breaker did not close during coast-down to maintain low flow conditions. The licensee reports the "B" recirculation pump functioned properly during subsequent test; and (3) The control rod drive (CRD) pump tripped on low suction pressure.
Subsequently, the licensee found and replaced a defective low 1
pressure switch.
The licensee declared an unusual event, which was terminated at 5:13 a.m.
(CDT).
At 12:26 a.m. (CDT) on June 15, 1986, River Bend Station experienced another J
unplanned trip due to operator error. At about 2% rated power, during reactor startup, an operator apparently opened the steamline drain valves prematurely.
This cuased a water level transient in the reactor vessel. The feedwater system then injected cold water, which increased reactivity, causing a neutron '
flux spike. The spike tripped the intermediate range monitors (IRM) on the upscale side.
j Trojan Nuclear Plant 1
In a letter dated June 16, 1986, the staff concluded that Portland General Electric Company (PGE) had adequately addressed the cause and effects of restrained thermal growth of the RCS due to steam generator snubber lock-up and has taken the necessary corrective actions to verify resolution of this issue for Trojan.
In addition, the staff concluded that modifications and repairs to the Trojan control room ventilation system and PGE's revised control room habitability (III.D.3.4) analysis meet the acceptance criteria of GDC 19 and that PGE had embarked upon a program that will significantly improve the quality of the Trojan control room ventilation system.
Based on these conclusions, the staff concurred in Trojan's restart from its 1986 refueling outage.
\\
JUNE 20, 1986 ENCLOSURE B
l South Texas Project Units 1 and 2 The ASLB has issued a Partial Initial Decision (1BP-86-15) dated June 13, 1986. The Decision implies that it covers both Phases Il a'nd III, although no hearings specifically denoted as Phase III have been held. The Board had mentioned earlier that there may not be a need for Phase III hearings. The rulings reflect favorably on the character and competence of the Applicant's management. The only items not closed relate to the use of probabilistic open items from the Safety EvaluHlon Report.
l Diablo Canyon Units 1 and 2 - Spent Fuel Pool Expansion i
On June 16, 1986 Mothers for Peace and Sierra Club (Intervenors) filed an Application for Stay with the Comission and the Licensing Board regarding license amendments for Diablo Canyon Units 1 and 2 authorizing expansion of the spent fuel pool for earh unit from 270 to 1329 fuel assembly storage locations. The Environrental Assessment and Amendments, including the staff safety evaluation and final no significant hazards consideration, were issued on l'ay 21 and May 30, 1986 respectively. The application for Stay is bas 3d on (1) assertions Act and NEPA requirements and (2) pplicable parts of the Atomic Energy that the NRC did not comply with a an affidavit by Dr. Ferguson asserting that the structural analysis did not include appropriate considerations such as the deletion of anchoring the racks to the floor and postulated combined motion of racks.
McGuire Unit 1 On May 18, 1986, the licensee phoned to inform the NRC of results of eddy current testing of the Unit I steam generator (SG) tubes:
Results of 100% eddy current testing of the tubes of the "D" SG revealed 136 tubes with indications within the tube sheet region in excess of the plugging depth limit of TS 4.4.5.4 (40% throughwall). Of these 136 tubes, 105 are located more than 2 inches below the top of the tube sheet. A 12% inspection of the "C" SG revealed 3 tubes in the tube sheet region requiring plugging, of which one was more than 2 inches l
below the top of the tube sheet. The 6% inspections of SGs "A" and "B" j
found no tubes requiring plugging.
In view of these results, the licensee plans to request a change to the plugging criteria in the technical specifications based upon a "P-star" criterion, similar (but more conservative) to that requested January 16, 1986 on Summer, and on an exigency basis.
JUNE 20, 1986 ENCLOSURE B
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8 NRC TMI-2 CLEANUP PROJECT blRECTORATE WEEKLY STATUS REPORT FOR JUNE 16 '- JUNE 22, 1986 lA I
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1.
DEFUEL'ING Wl a
s 3
s Pick and place defueling act vities continued during the week but 1
Q were suspended near the end of the weekito clean and str,ip.the work F
platform in preparation forfreieiving the drilling rig' forlore stratification. One additions 1' canister wa transferred to the fuel pool bringing the total numbeh of canistersytransferred tM43.
Two a'dditional internals vent valves were removed. Removal'of n
additional vent valves will be schedeled afte'?the core l boring..%
r On Sunday, June 15, 1986 a small piece of.fueNaterial was hand 1'ed' \\.
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without proper radiological controls evaluation.V. A.pfece,of fuel fell onto the defueling platferm when removing a defuelir.g tool from the reactor. The radiological' controls technician, wicking on the defueling platform perfonned an initial survey of the material and obtained a reading of greater than 5 R/hr. on contset. Without further. survey or direction,' the technician placed the ' particle back~
in' the vessel using thick rybber gloves and a towel; A second piece of material was discovered on June 17, 1966~and returned to the vessel., Proper surveys were performed in this case and the particle was remotely replaced. No additional dxposure resulted on June 17.
~
The licensee, at NRC request, took immediate corrective abtions to j
prevent Feoccurrence. These actions included performing a dose assessment for the individual involved in'the June 15 event, j
reinstructing all persons working in the reactor building and command centers on small particle hazards, and providing remote' tools to handle particles.,The preliminary dose. assessment for the individual'was 12 mrem. The NRC has confirmed that all other immediat.e corrective 1 actions have been completed. Assign'ed Health Physics Specialists are conducting a special inspection regarding the event.
2.
PLANT STATUS,
7
'The react # remains in long term cold shutdown, vented to the atmosphere. Core cooling is by natural-heat loss to ambient bGilding atmosphere. The average incore thermocouple reading is 80 F.
The airbo,rne radioactivity on the defueling platform is about 3 E-7 uti/cc Tritium and 4 E-10 uCi/cc particulates, predominately Cesium-137 and Strontium-90.. The platform is mounted above the modified internals indexing fixture which is mounted over the reactor veshel. These provide about 15 feet of water over the core region and 6 feet over the carousel holding the defueling canisters.
t JUNE 20,1986 ENCLOSURE B s
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13.
WASTE MANAGEMENT The Submerged Demineralizer System (SDS) is continuing to process batch S-133.
SDS processing to date has been 4,011,603 ga.11ons.
EPICOR II completed processing batch 290, 291, and 292. The system g
has processed 2,969,106 gallons tc date.
f 4.
ENVIRONMENTAL MONITORING US Environmental Protection Agency (EPA) sample analysis results show that TMI site liquid effluents are in accordance with l
j regulatory limits, NRC requirements, and The City of Lancaster Agreement.
The Lancaster water sample taken at the water works river intake and l
analyzed by EPA consisted of a seven day composite sample taken June 1 - 7, 1986. A gamma scan detected no reactor related activity.
TMI water samples taken by EPA at the plant discharge (includes Units 1 and 2) to the river consisted of seven daily composite samples taken from May 31 - June 7, 1986. A garna scan detected no reactor related activity.
The EPA analysis of the NRC outdoor air sample for the period June 13 - 19, 1986 showed that concentrations of Cs-137 and I-131 were below the lower limit of quantitative detectability for the system.
5.
AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES A fuel canister D-138 was aligned, grappled, and transferred from the west upender to a canister storage rack.
Assembly of the desludging system continued.
The testing program was completed on the transfer shield, cask upender, and other components needed to support fuel shipping and the system was turned over to plant operations for training.
6.
NRC EVALUATIONS IN PROGRESS i
Technical Specification Change Request number 49, and 51.
Recovery Operations Plan Change number 31, 33, 35, and 36.
Solid Waste Facility Technical Evaluation Report.
Reactor Building Sump Criticality Safety Evaluation Report.
Defueling Canister Technical Evaluation Report, Revision 2.
The Core Stratification Sample Acquisition, Revision 4 Safety Evaluation Report (SER) and the Canister Handling and Preparation for Shipment SER were issued on June 19 and June 20, 1986, respectively. The Core Stratification Sample SER includes a provision for leaving a drill casing in the damaged core rubble to allow television camera access to the lower core regions. The 1
Canister Handling and Preparation for Shipment SER discusses fuel canister movement from the dewatering station to the shipping cask.
JUNE 20, 1986 ENCLOSURE B
4 1
l 0FFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS l
Items of Interest l
i Week Ending June 20, 1986 Near-Term Actions Under the NWPA Section:
121(a) of NWPA:
EPA Final HLW Standards Status: The proposed Federal Register Notice of revisions to conform 10 CFR Part 60 to EPA Standards (SECY 86-92) was submitted to the Commission in late March 1986, and approved on May 15, 1986.
Action:
The proposed rule is scheduled for publication in the Federal Register on June 19, 1986.
Section:
114(e)(2) of NWPA:
Federal Agency Reporting Requirements Status:
With issuance of the DOE final PDS on April 3, 1986, the reporting requirements of Section 114(e)(2) are now effective.
Any Federal agency that determines that it cannot comply with any deadline in the final PDS, or fails to comply, is required to submit a report to the Secretary of Energy and to Congress explaining the reason j
for actual or potential noncompliance.
Action:
In the final PDS, NRC was scheduled to " Issue Proposed Amendment to Conform 10 CFR Part 60 to EPA Standards" in March 1986. The proposed revisions will be published June 19, 1986 (see above).
Section:
141 of NWPA:
Monitored Retrievable Storage (MRS)
Status:
DOE had planned on submitting the MRS proposal and NRC comments to Congress in early February 1986.
However, an injunction on behalf i
of the State of Tennessee has delayed the submittal of the proposal indefinitely.
Action:
DOE has filed an appeal to expedite a decision on the injunction in the Sixth Circuit Court of Appeals in Cincinnati, Ohio, and oral arguments are scheduled to begin July 21, 1986.
l Section:
141(d) of NWPA:
Licensing of MRS i
Status:
NRC developed revisions to 10 CFR Part 72 to provide the licensing framework for the MRS, should it be authorized by Congress.
JUNE 20, 1986 ENCLOSURE C
Action:
The Staff Requirements Memo (SRM) was received on April 21, 1986 and proposed revisions were published in the Federal Register on May 27, 1986 (51 FR 19106).
Section:
306 of NWPA:
Regulations for Training Power Plant Personnel Status:
The final rulemaking on Part 55 and three associated regulatory guides concerning regulations for Training of Power Plant Person-
)
nel were submitted to the Commission on April 18, 1986 (SECY 86-123)
)
and are currently awaiting Commission approval.
1 Near-Term DOE Actions of Interest May 28, 1986 DOE recommended Washington, Nevada, and Texas for site characterization.
4 May 28, 1986 DOE announced an indefinite delay in the second Repository Crystalline Project Issue Request for Proposal (RFP) for Transportation June 1986 Cask Development l
Sequoyah Fuels Corporation During the week of June 9, 1986, Region IV conducted a closeout inspection of Kerr-McGee's Sequoyah Fuels UF production facility in Gore, Oklahoma.
NMSS staffparticipatedinthiseffbrtinordertoreviewthestatusofplantsafety modifications, procedures, training, commitments, recommendations, and contin-gency planning related to startup of UF production.
During the exit briefing g
held June 12, 1986, several of the appr5ximately 30 open items generated from the January 1986 inspection were closed out, however, many remain.
In addition, procedures and training commitments remain to be completed and the dedicated safety and emergency equipment have not yet been received.
An earlier test of the contingency plan's public notification system indicated problems which remain to be resolved.
Contract for Assessment of Risks to Public Health and Safety From Transportation of Radioactive Materials The NMSS Transportation Integration Project is proposing to undertake a contrac-tual study of the risks to public health and safety from the transportation of radioactive materials in the period 1985-2005 when NWPA activities reach full operating levels.
On June 16, 1986, the Waste Management Review Group approved the proposal to have this study performed by the Center for Nuclear Waste Regu-latory Analysis as soon as the contract is approved and operation of the Center begins.
This will occur about the first of 1987, according to present scheduling.
The study is planned to provide information for use in licensing reviews for the high-level waste respository, the MRS facility (if authorf zed by Congress), and the transportation system which 00E will provide to meet NWPA requirements.
JUNE 20, 1986 ENCLOSURE C
NRC-DOE Transportation Meeting on Nuclear Waste Policy Act (NWPA)
On June 12, 1986, members of the Transportation Certification Branch met with representatives of DOE to discuss the technical aspects of the Request for Pro-posal for DOE to obtain shipping casks under the NWPA.
DOE intends to procure a variety of different cask designs to meet its shipping needs.
Distribution of Radioactive Topaz Gems It recently came to the attention of NMSS that at least one research reactor is irradiating gemstones and distributing them with induced radioactivity.
Other reactors have called and expressed interest in the same activity.
A Part 32 license is required to distribute radioactive consumer products, and no reactor possesses such a license.
NMSS has never issued a license authori-zing the distribution of radioactive gems, because of the Commission policy against allowing distribution of radioactive toys, novelties, or adornments.
Region III inspection staff is taking appropriate enforcement action with respect to the research reactor that we know is distributing radioactive gems.
They are also asking the other Regions to check other reactors.
NRR is pre-paring a generic letter to all research reactors reminding them of NRC require-ments on distribution of radioactive products to unlicensed persons.
The staff is further evaluating whether DOE reactors and/or imported gems may be involved, and whether it may be permissible to hold irradiated gems until the radioactivity decays away.
FBI Legislation In anticipation that the House will pass legislation providing licensee access to FBI criminal records, staff has drafted conforming rule requirements and is preparing a rule package for review and comment.
Japanese Visit On June 19, 1986, Mr. George McCorkle and Mr. Robert Skelton briefed Mr.
Fukushima, the Deputy Director of the Safety Planning Division, Safety Bureau, Japanese National Policy Agency on NRC's involvement in security at nuclear facilities.
Safeguards Regulatory Effectiveness Review (RER) at TMI The NMSS Safeguards staff, assisted by U.S. Army Special Foices personnel, conducted an RER at the Three Mile Island nuclear power plant June 9 through June 13, 1986.
The team was accompanied by two staff members of OIA and representatives from IE and Region I.
JUNE. 20,1986 ENCLOSURE C
NRC-DOE Physical Security Comparability Study The second meeting of the NRC DOE Physical Security Comparability Study Team is scheduled to be held on July 2, 1986, in Germantown, MD.
The purpose of the meeting is to finalize the list of DOE facilities to be studied and the criteria to be used for data gathering.
Tentative plans have been made to visit a DOE facility during the week of July 7.
Spent Fuel Rule Final revisions were being made to the rule when it was learned that cast iron shipping casks might be approved for shipping spent fuel, as requested by a recent applicant.
The rule has been held up pending a sabotage analysis of cast iron casks.
i l
l JUNE 20, 1986 ENCLOSURE C i
Office of Inspection and Enforcement Items of Interest Week Ending June 20, 1986 1.
The following Significant Enforcement Actions were taken during the past week:
a.
An Order to Show Cause Why the License Should not be Modiified and a Notice of Violation and Proposed Imposition of Civil Penalty was issued to Hercy Hospital (Wilkes Barre, PA) in the amount of $5,000.
This action was based on a misadministration, the failure to report same, and willfully making a material false statement when questioned during the course of an inspection (EN 86-39).
b.
An Order to Show Cause Why the License Should not be Modified was issued to the Valley Radiology Associates, Inc. (Kingston, PA). This action was based on a deliberate violation of an NRC requirement in not reporting a misadministration to the NRC and the referring physician. The alleged misadministration took place at Mercy Hospital where the Radiation Safety Officer serves in the same capacity as at Valley Radiology Associates, Inc. (EN 86-40).
2.
The following IE Preliminary Notifications were issued during the past week:
a.
PNO-I-86-41, Swatch Watch, USA, Inc., New York, NY - Distribution of Watches Containing Tritium Without an NRC License.
b.
PNO-I-86-41A, Swatch Watch, USA, Inc. (New York, NY), Distribution of Watches Containing Tritium (Update).
c.
PNO-I-86-42, Niagara Mohawk Power Corporation (Nine Mile Point 2) -
Office of Investigation Report on Harassment and Intimidation.
d.
PNO-I-86-43, Philadelphia Electric Company (Peach Bottom 2), Unplanned Shutdown Due to Loss of Emergency Service Water.
e.
PNO-II-86-41, Duke Power Company (Catawba 1) - Leak Inside Contain-ment and Unscheduled Shutdown.
f.
PNO-II-86-42, Virginia Electric and Power Company (Surry 2),
Unscheduled Shutdown Longer Than 48 Hours.
g.
PNO-II-86-43, Carolina Power and Light Company (Brusnwick 2),
Unscheduled Shutdown Longer Than 48 Hours.
h.
PN0-V-86-32, Southern California Edison Company (San Onofre 2) -
Startup Following Second Refueling Outage.
1.
PNO-V-86-33, Portland General Electric Company (Trojan) - Criticality After Refueling Outage for Cycle 9.
J.
PNS-V-86-05, Arizona Nuclear Power Project (Palo Verde 3), Suspected Attempted Sabotage / Vandalism.
JUNE 20, 1986 ENCLOSURE D
3.
The following IE Information Notices and IE Bulletins were issued during the past week:
a.
IE Information Notice No. 86-49, Age / Environment Induced Electrical Cable Failures, was issued to all nuclear power reactor facilities holding an operating license or a construction permit.
l b.
IE Information Notice No. 86-50, Inadequate Testing to Detect
]
Failures of Safety-Related Pneumatic Components or Systems, was j
issued to all nuclear power reactor facilities holding an operating license or a construction permit.
c.
IE Information Notice No. 86-51, Excessive Pneumatic Leakage in the Automatic Depressurization System was issued to all boiling water reactor nuclear power facilities holding an operating license or construction permit.
4.
Other Items a.
Senior Management Meetings (1) Director, IE participated in an enforcement conference in Region II.
(2) Director, IE participated in the exit meeting of the Design Control review at Sequoyah.
b.
TVA Activities Members of the Engineering and Generic Consnunicatfor.s Branch and the Reactor Construction Programs Branch participated in a review of welds documentation at Sequoyah this week, c.
Incident Response (1) The Incident Response Branch has been participating for the NRC, in a limited manner, in the FEMA Continuity of Government Exercise REX 86 BRAV0. The exercise began on June 10 and will continue until June 23.
(2) The Emergency Response Coordinators Workshop #12 was held in Region III. Representatives from the Division of Emergency l
Preparedness and Engineering Response and all of the regional offices attended. The topics discussed during this counter-part meeting included emergency preparedness interface with incident response, Chernobyl response efforts, review of assessment program, continued development of regional response position guidance, and response training programs.
(3)
In connection with the ERC workshop, an NRC Task Group on U.S./ Canadian Interfaces During a Radiological Emergency met in Region III on June 19, 1986. The task group is composed of representatives from Regions I, III, V, IE, and IP. They discussed existing arrangements and potential future measures i
that should be considered for radiological emergencies in the U.S. or Canada.
JUNE 20, 1986 ENCLOSURE D
d.
Emergency Preparedness Emergency Preparedness Branch members are supporting regional staff in the evaluation of annual emergency preparedness exercises at FitzPatrick, North Anna, Crystal River, and Prairie Island, e.
Meetings--Conferences of Note (1) Staff members of the Engineering and Generic Communications Branch participated in the ANSI /ASME B16 Subcommittee N (Steel Valves) meeting in Alexandria, VA.
(2) Staff members of the Operating Reactors Program Branch parti-cipated in the Region III Resident Inspector's Meeting and presented a training session on the Safety System Functional Inspection concept.
f.
Quality Assurance (1) Members of the Quality Assurance Branch inspected the TERA quality assurance program implementation as it applies to the Comanche Peak Design Adequacy Program. This program is being conducted by TERA as part of the Comanche Peak Response Team (CPRT) effort. Representatives of Region IV and the Vendor Branch are also participating.
(2) The Quality Assurance Branch inspection of the Sequoyah Design Baseline and Verification Program and the Engineering Assurance oversight of the program that began on June 10 concluded this week. The IE team will exit on June 20.
(3) Members of the Quality Assurance Branch will meet with the TVA Engineering Assurance Division to discuss, on a preliminary basis, the program equivalent of the Sequoyah Design Baseline and Verification Program that will be used at Watts Bar.
(4) A Quality Assurance Branch inspection of the Beaver Valley 2 Engineerins Assurance Program was conducted the week of June 2 at the offices of Stone and Webster.
g.
Vendor Program (1) Members of the Vendor Program Branch are conducting an inspec-tion starting this weekend at Nuclear Packaging Incorporated (NUPAC), a manufacturer of transportation casks. The purpose of the inspection is to review on an expedited basis, open items from a previous inspection regarding the casks to be used in the TMI-2 defueling.
(2) The following Vendor Program Branch inspections are being conducted this week:
Surry 1 and 2, Gravel Neck, VA - to review the equipment qualification program and its implementation to determine conformance with the requirements of 10 CFR 50.49.
JUNE 20, 1986 ENCLOSURE D
Consolidated Pipe & Valve Supply, Mishawaka, IN - followup to inspection at Golden Gate Forge & Flange and to review implementation of quality assurance program pertaining to Section III orders.
h.
Generic Issues A potential generic concern is under consideration related to BWR licensees' response to a primary system leak typified by Cooper's response to a 3.8 gpm leak on June 16, 1986.
Typical response is to begin de-inerting before shutdown to facilitate identification of leak source by a containment entry and minimize down time if J
shutdown is required. Based on leak-before-break considerations, containment potentially is made most vulnerable when it is the most likely to be called upon (for piping failures). A proposed generic issue is being drafted.
i JUNE 20, 1986 ENCLOSURE D
OFFICE OF NUCLEAR REGULATORY RESEARCH Items of Interest Week Ending June 20, 1986 Review of Indonesian Radiation Protection Program From May 15 to June 15, 1986, R. E. Alexander, RES visited Indonesia under the auspices of_the IAEA. The Indonesia Atomic Energy Comission (BATAN) requested Mr. Alexander's review and make recommendations regarding their plans for radiation protection at an extensive nuclear research center now under construction near Jakarta. A more general review of BATAN's national radiation protection regulatory program was also requested, along with a series of lectures on radiation risk assessment, emergency planning, and the most recent recommendations of the ICRP. These lectures were presented at BATAN Headquarters, at the new research center, at existing BATAN centers of Bandung and Yogyakarta, and at the Bandung Institute of Technology.
Industry Use of NUREG/CR-4373 In December 1985, NUREG/CR-4373 (entitled, " Compendium of Cost-Effectiveness Evaluations of Modifications for Dose Reduction at Nuclear Power Plants") was issued. This report, which was prepared by Brookhaven National Laboratory (BNL) for RES, identifies cost-effective modifications which can reduce employee exposures at nuclear power plants. Subsequently, the staff of the Atomic Industrial Forum has conducted an independent survey on the usefulness of the report.
Initial responses to this survey from six utilities, reflecting experience at 21 plants, revealed that some utilities have implemented many of the recommended modifications, others have been recommended for implementation and some were judged not cost-effective at specific sites.
It is clear that the document and its review have sparked the interest of some utilities to consider a number of modifications not previously considered.
For example, one utility listed 23 such items. While this is a small sample of results, it suggests considerable interest on the part of the utilities in reducing worker exposures. The study and report seem to be serving a very useful role in stimulating the corporate and plant nuclear engineers to consider more fully dose reduction possibilities and thier cost-effectiveness.
I JUNE 20, 1986 ENCLOSURE E
- Bankruptcy Rule The proposed rule entitled, " Bankruptcy Filing; Notification Requirements" is presently with ADM in preparation for publication in the Federal Register.
It sets forth amendments to 10 CFR Parts 30, 40, 50, 61, 70, and 72 that would require licensees to notify the NRC in the event that a bankruptcy petition is filed involving the licensee. The proposed rule is necessary because a licensee's severe financial condition could affect its ability to handle licensed radioactive material and the NRC must be notified so that timely and appropriate measures to protect the public health and safety can be taken.
HDR Update In cooperation with KfK, Federal Republic of Germany, we are participating in the high level vibration experiments at the HDR facility near Frankfurt, FRG.
The objective is to validate predictive methods into the inelastic range, evaluate stiff versus flexible piping and evaluate the behavior of a Shippingport valve under flow and vibration conditions. The experiments were started on June 3, on schedule. However, on June 16, the nearby VAK reactor (shutdown with fuel in the storage pool) reported distorted tiles in the spent fuel pool. This problem occurred in 1976 and most of the pool was retiled.
The currently observed distortions are in the approximately 10% of the pool wall that was not retiled. We and the KfK staff do not believe the HDR shaker could cause any significant vibration at the VAK and measurements taken during the tests confirm this.
Nonetheless, this is a sensitive problem. The " Green Party" has had demonstrators near the HDR site. The HDR tests were halted, pending resolution of discussions between KfK and the Bavarian TUV. A fix has been proposed to insure that should a tile come loose it would be retained by a barrier device. This barrier is scheduled for installation on June 20. A meeting with the TUV is scheduled for June 23 and a restart of testing is planned for June 24. We have decided not to send Jim Costello to HDR until the issue is resolved.
NUREG-0956 During the week of May 27, M. Silberberg, J. Mitchell, and R. Meyer presented briefings at four national laboratories on the near-final version of NUREG-0956. A similar meeting was held on June 3 with two ACRS subcommittees (Severe Accidents Subcommittee and Nuclear Plant Chemistry Subcommittee). On June 6, a brief meeting was held with the full ACRS committee to discuss the disposition of previous ACRS comments on draft NUREG-0956 and to note the key messages from the report.
Letters commenting on NUREG-0956 were requested from the four national laboratories, from Battelle Columbus, and from the ACRS. The letters from the laboratories have now been received and are overall positive and supportive, although some changes will be required in NUREG-0956 to satisfy conditions of i
the endorsements. Work is underway to make these changes, but this level of j
l JUNE 20, 1986 ENCLOSURE E
. laboratory review was not included in the staff's original schedule for NUREG-0956 and some delays might occur although publication in July-is still expected.
The ACRS letter has also been received. While the ACRS letter states that they consider the final version of the report to be superior to the earlier draft, no other general conclusions are stated.
Instead, ten comments are made about the report and the source term work in general. This recent ACRS letter and the disposition of the ten comments will be included as a new appendix in the final version of NUREG-0956.
Recently Issued Publications Proposed Rev. 3 to Reg. Guide 1.63, Electric Penetration Assemblies in Containment Structures for Nuclear Power Plants, Task EE 405-4. Comments requested by August 25, 1986.
Contact:
S. K. Aggarwal (391) 443-7668.
Reg. Guide 7.10, Rev. 1, Establishing Quality Assurance Programs for Packaging Used in the Transport of Radioactive Material.
JUNE 20, 1986 ENCLOSURE E
. RES RULEMAKING ACTIVITIES AND OTHER RELATED ISSUES Notification of NRC of Cases of Bankruptcy Filing (Parts 30,40,61,70,72)
The proposed rule would require licensees to notify the appropriate regional office of the NRC within a certain time period in the event of a bankruptcy proceeding involving the licensee. Notification of the NRC in cases of bankruptcy would alert the Commission so that it may deal with potential hazards to the public health and safety posed by a licensee that does not have the resources to properly handle licensed radioactive material or clean up possible contamination.
The EDO on June 9,1986, approved for publication the proposed rule entitled
" Bankruptcy Filing; Notification Requirements" which sets forth amendments to 10 CFR Parts 30, 40, 50, 61, 70, and 72.
Procedural Amendments Dealing with Site Characterization and the Participation of States and Indian Tribes in the Siting and Development of High Level Waste Geologic Repositories (Part 60)
The proposed rule would revise procedures regarding NRC reviews of license applications for disposal of high-level radioactive wastes in geologic repositories. The procedures are being revised principally to conform to the provisions of the Nuclear Waste Policy Act of 1982. Specifically, the proposed rule would clarify that NRC begins its review in this licensing process after i
DOE provides NRC a site characterization plan and that usual rules of practice apply to licensing of these repositories.
The Commission voted to approve the effective amendments but with certain changes to what was recommended by the staff. SECY is evaluating the revised Federal Register notice in light of the staff requirements memo. The staff has completed revising the analysis of public comments document so that it conforms to the Commission's changes. The Commission staff is working on another staff requirements memo involving issues of Indian tribes' definitions raised by the staff.
JUNE 20, 1986 ENCLOSURE E
, 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 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.
Work continues on the development of technical position papers for the principal parameters affecting the risk estimates. While consensus is being reached on a number of these issues, some (such as direct heating) are not i
resolved at present.
It is hoped that all issues will be resolved within the next few weeks, but it is not clear at present whether there will be
.I substantial differences between the staff's positions and the contractor's.
If there are substantial differences that must be analyzed for NUREG-1150, it is likely that this would threaten the September 30 publication date for the draft.
1
)
JUNE 20, 1986 ENCLOSURE E
l ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING JUNE 20, 1986 I
i Foreign Visitors On Thursday Messrs. G. Manfredini and F. Muzzi of ENEL (Italy's electric power authority) visited NRR to discuss seismic issues and related soil improvement techniques. Leon Reiter and Lyman Heller met with the visitors.
On Thursday Mr. Matsuomi Fukushima of Japan's national policy agency met with R. Skelton and G. W. McCorkle of NMSS to discuss security alarm i
systems and U.S. legislation affecting their use. The visit was i
arranged by the Washington office of the International Association of j
Chiefs of Police.
I On Thursday Mr. Christopher Audland, Director General for Energy of the 1
Comission of the European Communities (CEC), and four other CEC l
officials met with Chairman Palladino, Comissioner Zech and IP Director Shea to discuss international effects of Chernobyl and other topics of mutual interest.
l On Thursday Dr. Morris Rosen, Assistant Deputy Director General of the j
Department of Nuclear Energy and Safety at the International Atomic Energy Agency (IAEA), met with all of the Comissioners NRR Director i
Denton and IP Director Shea to discuss the accident at Chernobyl and strengthening of the IAEA's safety activities.
On Friday Dr. Peter Tempus, Deputy Director General for Safeguards at l
the IAEA, met with Chairman Palladino, Comissioners Asselstine, Bernthal and Zech, IP Director Shea, and NMSS and IP staff members to discuss the international safeguards program.
i l
I 1
i JUNE 20, 1986 ENCLOSURE G 1
t OFFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA ITEMS OF INTEREST Week Ending June 20, 1986
" Report on 1985 Nonreactor Events and Five-Year Assessment for 1981-1985" (AE0D/N601) was issued on June 17, 1986. The report contains a review of 170 reports of events that occurred during 1985 and a review of the reports received in the five-year period from 1981-1985. The number and type of events reported i
in 1985 did not differ substantially from those received in other years, Overexposures of radiographers continue to account for the most significant i
personnel overexposures reported. The Radiography Steering Committee chaired by the NRC's Office of Nuclear Material Safety and Safeguards has been looking at ways to reduce these overexposures.
1 r
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JUNE 20, 1986 ENCLOSURE J l
DEPUTY EXECUTIVE DIRECTOR FOR REGIONAL OPERATIONS AND GENERIC REQUIREMENTS (DEDROGR)
Week Ending June 20, 1986 CRGR Attached is a sumary of the CRGR activities for the period May 1 through Background material on topics reviewed by the Comittee May 31, 1986.
Copies are and the minutes of CRGR meetings are sent to the Commission.
J provided to the Public Document Room after the NRC has considered (in a public Questions concerning i
forum) or decided the matter addressed by the documents.
this monthly report should be referred to Walt Schwink (492-8639).
i
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i JUNE 20, 1986 ENCLOSURE M
Dato: June 20, 1986 Page 1 ef 1 SUPMARY OF CRGR ACTIVITIES (May 1 through May 31, 1986)
E5 Meeting No.
8 Meeting Date (Annauncement CRGR CRGR Recommendation
'g Date)
Agenda Status to EDO EDO Action E
90 Briefing, Proposed Generic Complete CRGR suggested that the staff None required.
5/28/86 Letters 86-05 and 86-06 carefully review the language in Reactor Coolant Pump Trip Generic Letters 86-05 and 86-06 to BWR Piping, Draft NUREG-0313 assure that the staff intent for Revision 2 no new requirements was clearly conveyed.
-Sponsoring Office - NRR
-Category 2 Item
- Issue!39,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,
Review, Proposed Final Pending CRGR recommended that the RG No action required at Version of Regulatory Guide be modified to address the this time because RES (0P-713-4) Criteria for a Committee's comments and re-has nct yet taken a Establishing a Tritium Bioassay submitted to CRGR for further position on the CRGR Program review.
recommendations.
-Sponsoring Office - RES
-Category 2 Item
!!ssuef}32,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,
Review, Final Version of Pending CRGR recommended that the rule No action required at Rev. to Property Insurance be modified to reflect CRGR this time because SP Rule reconnendations and resubmitted has not yet taken a for CRGR further review.
position on the CRGR recommendations
-Sponsoring Office - SP
-Category 2 Item M
-Issue #33 5
- E$
=
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ITEMS ADDRESSED BY THE COpMISSION - WEEK ENDING JUNE 20, 1986 STAFF REC'UIREMENTS - BRIEFING BY STAFF ON STATUS OF TVA,10:00 A.M.,
1 A.
FRIDAY, iUNE 6. L986, 00pWISSIONER5' CONFERENCE ROOM, D.C. OFFICE (PORTION OPEN TO PUBLIC A itNDANCE) Mann SECY for the Record dated 6/19/86 t
The Commission
- was briefed by the staff on the staff's ongoing review of TVA and staff's preliminary evaluation of.TVA's corporate nuclear performance plan.
There were no requirements for the staff at this session of the meeting.
i
- Commissioner Zech was not present.
i STAFF RECUIREMENTS - BRIEFING BY DAVIS-BESSE AD HOC REVIEW GROUP, 2:00 P.M.,
B.
FRIDAY, C UNE 6,1986 COMI55IONER5' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC AlltNDANCE) Mamn SECY to Stello dated 6/19/86 The Commission was briefed by the Davis-Besse Ad Hoc Review Group on the Group's May 2, 1986 report on the June 9, 1985 loss of feedwater event that occurred at the Davis-Besse Nuclear Power Plant.
The Commission directs the staff to review the Ad Hoc Group's report and submit to the Conunission an action plan and recommen-1 dations for Commission review.
C.
STAFF REQUIREMENTS - BRIEFING ON RESTART OF SAN ONOFRE-1, 2:00 P.M.,
THURSDAY, JUNE 12, 1986. COMMISSIONERS' C0t:FERENCE ROOM, D.C. OFFICE j
(OPEN TO PUBLIC AIitNDANCE) Memo SECY to Stello dated 6/19/86 The Commission was briefed by the licensee and the staff on the l
status of San Onofre Unit 1 for return to power following the water hammer event of November 21, 1985, which occurred in the feedwater system.
Presentations for the licensee were made by i
D. Fogerty Executive Vice President Southern California Edison i
K. Baskin Vice President for Nuclear Engineering, Safety & Licensing Southern California Edison M. Medford Manager of Nuclear Safety Southern California Edison j
J. Rainsberry Licensing Superintendent San Diego Gas and Electric I
JUNE 20, 1986 ENCLOSURE O i
5
Presentations for the staff were made by:
Victor Stallo, Jr.
John Martin Ellis Merschoff
~
Richard Dudley James Milhoan The Commission discussed whether a need existed for voting on the San Onofre-1 restart.
Subsequent to the meeting, the Commission has concluded that it need not vote on the restart of San Onofre-1.
The EDO, however, is to inform the Commission when he is ready to permit San,onofre-1 to return to power.
i i
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ENCLOSURE O JUNE 20, 1986
n 4
-m E
NRR MEETING NOTICES
- JUNE 20, 1986 1
ti; DOCKET APPLICANT /
DATE/ TIME NLMBER LOCATION PURPOSE' ATTENDEES NRR CONTACT q
6/23/86 50-029 Room 6110 Discuss proposed corrective NRC/YAEC E. M. McKenna 1:00 p.m.
Maryland National actions relating to design Bank Building problem in electrical distri-bution system 1
6/24/86 50-206 Room 6110 Discuss control room habit-NRC/SCE E. M. McKenna 9:00 a.m.
Maryland National ability requirements l
Bank Building
-Room 6110 Discuss the CE Owners Group NRC/CE Owners W. A. Paulson I
6/26/86 9:30 a.m.
Maryland National position concerning auxiliary Group Bank Building feedwater diversity for newer i
plants with regard to the ATWS rule 7/1/86 50-412 Room P-110 Discuss with DLC technical NRC/DLC P. S. Tam 9:00 a.m.
Phillips Building issues raised by the staff regarding DLC's Equipment Qualification Report (sub-mitted May 23,1986)
)
7/1/86 50-272 Room 6110 Discuss DCRDR NRC/PSE&G
- 0. C. Fischer 9:00 a.m.
50-311 Maryland National g
Bank Building n
r-8 I,
E m
m i
Copies of summaries of these meetings will be made publicly available and placed in the respective docket file (s) in the NRC-and local public document rooms 4
FOR WEEK ENDING: 6/20/86 N
M Divisi*on of Fuel Cycle and Material Safety E$
ATTENDEES /
DOCKET g
DATE/ TIE NUPSER LOCATION PURPOSE APPLICANT NRC CONTACT.
8 6/24/86 Washington, To meet with members of a new P. Vacca (FC)
Vacca 5:00 pm DC management team for Syncor (a Reps of Syncor Hyatt-Regency consercial nuclear pharmacy);
Hotel (Syncor staff in. DC to attend annual meeting of Society of Nuclear Medicine).
6/26/86 Silver To meet with members of the FDA P. Vacca (FC)
Vacca 9-11:00 am Spring, MD staff to discuss regulation of S. Baggett (FC) 87S7 Ga. Ave, bone itineral analyzers.
Reps of FDA f
Division of Waste Management July 6-13 Paris, France To attend NEA meeting and visit REBrowning REBrowning Normandy, France Lamanche 11w facility Braunschweig, GR 1
Division of Safeguards 4
None.
g n
y i
1,
m e-
6 RES MEETING NOTICES June 20,1986 5
ATTENDEES /
g DATE/ TIME
. LOCATION PURPOSE
. APPLICANT NRC CONTACT i
6/29-7/3 San Antonio, TX 19th National Fracture Mechanics Vagins Vagins Symposium 6/30-7/2 Columbus, OH ACRS Metal Components Subcommittee Mayfield Arlotto Meeting 1
6/29-7/6 Paris, London OECD in Paris Serpan Serpan UKAEA in London i
7/1/86 Columbus, OH ACRS Subcommittee Meeting on Piping Mayfield Arlotto Research Programs
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