ML20137V534
| ML20137V534 | |
| Person / Time | |
|---|---|
| Issue date: | 10/02/1985 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-850927, NUDOCS 8510040063 | |
| Download: ML20137V534 (51) | |
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October 2, 1985 For:
The Comissicners From:
T. A. Rehm, Assistant for Operations, Office of the EDO
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING SEPTEMBER 27, 1985 A summary of key events is included as a convenience to those Commissioners who may prefer a condensed version of this report.
Contents Enclosure
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Administration A
Nuclear Reactor Regulation B
Nuclear Material Safety and Safeguards C
Inspection and Enforcement D
Nuclear Regalatory Research E
Executive Legal Director F*
International Programs G
State Programs H
Resource Management I
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Analysis and Evaluation of Operational Data J*
Small & Disadvantaged Business Utilization & Civil Rights K*
Regional Offices L
CRGR Monthly Report M*
Executive Director for Operations N*
Items Addressed by the Comission 0
Meeting Notices P
Proprietary or Other Sensitive Information (Not for Q
external distribution)
- No input this week.
l B51004 851002 T. A. Rehm. Assistant for Operations PDR C
NRCC Office of the Eyecutive Director WEEKLYINFOREPT pop for Operations
Contact:
T. A. Rehm. ED0 492-7781
,bi HIGHLIGHTS OF WEEKLY INFORMATION REPORT WEEK ENDING SEPTEMBER 27, 1985 Shoreham The licensee declared an Unusual Event and commenced on unplanned reactor shutdown on September 25 when two ECCS systems became inoperable.
The HPCI turbine was inoperable for the performance of hot alignment checks, and the RHR system was being shutdown after being used for suppression pool cooling, when it discovered that the RHR pump bypass valve could not be shut. The RHR pump also serves as the LPCI purp.
The three inch bypass valve actuator was found to be separated from the valve body. The four actuator mounting bolts appeared to have sheared off. The licensee returned the HPCI turbine to service within about I hour and 15 minutes and stopped the reactor shutdown. The actuator failure is being investigated, b
EPA Standards for Radon Emissions from Active Uranium Mills In a Federal Register notice on Wednesday, October 31, 1984, EPA is, sued an advance notice of proposed rulemaking (ANPRM) for setting standards to control radon releases from licensed uranium mills during operations.
These releases are now addressed in NRC and EPA rules as releases to be kept ALARA.
The new EPA standards will be issued under Section 112 of the Clean Air Act, not the Atomic Energy Act, as amended.
The driving force for prompt action is an agreement filed with the U. S. District Court for the Northern District of California.
The agreement was negotiated with the Sierra Club and filed with the court to avert suit by the Sierra Club.
EPA outlined their present plan at an informal meeting with NRC staff Monday, September 23, 1985.
EPA plans to issue a work practices standard and prescribe different standards for existing and new facilities.
EPA's schedule is to issue proposed rules in January,1986, hold hearings in February, and issue final rules by May 1, 1986. NRC described current practices at the sites to control radon releases-
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during operation and encouraged flexibility in whatever standards are issued.
Staff members of both agencies agreed that continued interaction on the rule-making was desirable.
Trip to Wood County, West Virainia and Canonsbura, Pennsylvania A FC ttaff member visited the AMAX Inc., site in Wood County, West Virginia to obserst t'.1e condition of the stabilized site and then attend meetings at Canonst,urg, Ppnnsylvania, with representatives of DOE to discuss site certification'ard to tour the Canonsburg site.
The Canonsburg site remedial action will be completed in November 1985 and will be the first DOE UMTRCA Title I site to be completed.
Sequoyah Fuel Corporation Materials License 5U8-1010 for Sequoyah Fuels Corporation was renewed on September 20,1985, for a 5 year term expiring September 30, 1990.
This action followed preparation of a Safety Evaluation Report, an Environmental Assessment (NUREG-1157), and publication of a " Finding of No Significant Impact" in the Federal Register on September 13, 1985.
The licensa authorizes Sequoyah Fuels to receive, sample, and convert yellowcake to uranium hexafluoride.
SEP 2 71985
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OFFICE OF ADMINISTRATION Week Ending September 27, 1985 ADMINISTRATION OF THE FREEDOM OF INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Carryovers, 1984 179 23 Received, 1985 657 39 Granted 528 27 Denied 145 14 Pending 163 21 ACTIONS THIS WEEK
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Received Don L. Schlemer, Requests seven categories of records regarding Cleveland Government Electric Illuminating Company, Toledo Edison, North Accountability Holding Company, East Merger Company, and West Merger Project Company.
(85-642)
Charles Barnes Requests a list of active and inactive Docket 40 licenses (85-643) and all records from March 4, 1985, in Docket 40-8768, Sequoyah Fuels Corporation, not already publicly available regarding the concerns of a former Sequoyah
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employee and the NRC's Uranium Recovery Field Office's review and investigation of these concerns.
Charles Barnes Requests all records from June 25, 1975, through March 1 (85-644) 1976, related to a waste shipment at the Nuclear Engineering Company. Inc., Beatty, Nevada, burial site.
Jesse R. Meer, Requests copics of John Wendell Beaver's FOIA requests, Bishop Liberman, F01A-85-520, and NRC's responses,
& Cook (85-645)
Brian Balogh, Requests specific records from the inception of the ACRS The Brookings until September 1957.
Institute (85-646)
Melody C. Johnson Referral from the FBI of eight records regarding the (85-647)
Kerr-McGee Corporation's Cimarron Facility.
CONTACT:
J. M. Felton 492-7211 ENCLOSURE A SEP 2 71985 i
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Received, Cont'd Carol Lee, Requests a copy of contract No. NRC-33-85-327.
Alcalde, Henderson, O' Bannon & Rousselot (85-648)
Barbara Klier, Requests records related to 49 FR 44252, a notice of an Siemens Medical Abnormal Occurrence at the St. John's Medical Center Systems, Inc.
in Indiana.
(85-649)
Frank Ruswick, Requests three categories of records related to a West Michigan request by the utility to leave in place Environmental radioactively contaminated soil at the Big Rock Point Action Council nuclear power plant.
(85-650)
Marvin S. Lieberman, Requests copies of a Qualification Report For In Zuckert, Scoutt, Containment Radiation Monitoring, or a similar record, Rasenberger &
and any other records or infonnation submitted by GA Johnson Technologies (or General Atomics) concerning (85-651) instrumentation that can survive LOCA and qualification of equipment, instruments, or other devices under requirements of Reg Guide 1.97.
Jim Pedro, Requests a copy of WCAP-9964 entitled, " Iodine and NUS Corporation Cesium Spiking Source Terms for Accident Analysis."
(85-652)
Nina Bell, Requests three categories of records regarding NRC's Nuclear proposed rule on earthquakes and emergency planning.
Information and Resource Service (85-653)
Nina Bell, Requests five categories of records regarding Board Nuclear Notification No.85-081, " Allegations Concerning Information and Westinghouse Analyses and Quality Assurance," issued Resource Service on the Turkey Point nuclear power plant.
(85-654)
Nina Bell, Requests four categories of records related to quality Nuclear control at the Callaway nuclear power plant.
Information and Resource Service (85-655)
(NRCemployee)
Requests records providing the current grade, levels of (85-656) secretaries to five specified Directors.
Jim Pedro, Requests copies of two Westinghouse Owners Group Letters, NUS Corporation Nos. OG-110, " Evaluation of Alternate RCP Trip Criteria,"
(85-657) and 0G-137, " Response to NRC Question on RCP Trip."
ENCLOSURE A SEP 2 V 1985
3 Granted James E. Brunner, In response to a request for all records in the Consumers Power possession of the Advisory Committee on Reactor Company Safeguards regarding the Midland nuclear power plant, (85-602) made available 89 records.
Informed the requester that additional records subject to this request are already available at the PDR.
James F. Pierce, In response to a request for information regarding Environmental James Neel and/or David Gravely in their association Task Force with Pyrochem Inc., Nuclear Engineering, Inc., and (85-619)
U.S. Ecology, Inc., relating to the Maxey Flats Nuclear Disposal Area, Hillsboro, Kentucky, and the Sheffield, Illinois, disposal site, made available two records.
Informed the requester that additional records subject to this request are already available at the PDR.
Jean Whitney, In response to a request for a set of gumed mailing The_Keenan labels for IE Information Notices, made available a Corporation copy of the requested labels.
(85-634)
Pamela B. Jarvis, In response to a request for five categories of gummed Colorado State mailing labels, made available a copy of the University requested labels.
(85-635)
Michael O'Mealia, In response to a request for records containing the Doc-Search poss/ fail statistics for licensing and recualification Associates examinations given to reactor operators and senior (85-641) reactor operators at nuclear power plants subsequent to the issuance of SECY-84-81C, informed the requester that the requirement to report the licensing and requalification examination results to the Comission has been changed from a quarterly basis to an annual basis. The next examination results report will be sent to the Commission on December 15, 1985.
Barton A. Smith, In response to an APPEAL TO THE COMMISSION for the General Electric release of that portion of the denied transcript which Company included statements concerning spills or alleged spills (85-A-30-85-303) and any actions taken regarding the General Electric facility in North Carolina in 1984, made available 29 pages of the transcript.
Denied Nina Bell, In response to a request for three categories of records Nuclear related to the restart of the San Onofre Nuclear Information and Generating Station, Unit 1, made available 293 records, and Resource Informed the requester that additional records subject to Service this request are already available at the PDR. Denied (84-885) 43 records in their entirety and portions of five records pursuant to Exemption 5.
Denied portions of five records pursuant to Exemption 7A. Denied 124 records in
$EP 2 71985 their entirety pursuant to Exemptions 5, 6, 7A and 7C.
ENCLOSURE A
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Denied, Cont'd Durwood Zaelke, In response to a request for 12 categories of records Sierra Club related to the San Onofre Nuclear Generating Station, Legal Defense made available 10 records.
Informed the requester Fund that additional records subject to this request are (85-126) already available at the PDR. Denied 31 records in their entirety and portions of one record pursuant to Exemptions 5 and 7A. Denied one record in its entirety pursuant to Exemptions 5 and 7A of the Government in the Sunshine Act.
Lynn Cunningham, In response to a request for copies of draft and The Times-Picayune final letters from the NRC to Rep. Edward Markey Publishing concerning the Grand Gulf 1 nuclear power plant, made Corporation available 15 records.
Informed the requester that one (85-186) additional record subject to this request is already available at the PDR. Denied seven records in their entirety, release of which could allow those being l
investigated to learn the scope, direction, and focus of investigatory efforts and thus could possibly allow them to take action to shield potential wrongdoing or a violation of NRC requirements from investigators. Denied seven records in their entirety, release of which would tend to inhibit the open and frank exchange of ideas essential to the deliberative process.
1 Kathiann M. Kowalski, In response to a request for records relating to any Squire, Sanders investigations performed by or for the NRC or the AEC
& Dempsey with respect to possible unauthorized or unlawful burials (85-375) of radioactive source material at the Parkersburg site by Amax, Inc., and the relative completeness of Amax Specialty Metals Corporation's removal of Nigerian ore or other source material from the Parkersburg site to Morehead, Kentucky, in or about 1968, made available 36 records.
Informed the requester that we have referred one record to the EPA for a disclosure determination and direct response to her. Denied two records in their entirety, release of which would disclose the identity of a confidential source. Denied portions of 23 records, release of which would constitute a clearly unwarranted invasion of personal privacy.
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4 ENCLOSURE A SEP 2 71985
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r WEEKLY INFORMATION REPORT DIVISION OF CONTRACTS WEEK ENDING SEPTEMBER 27, 1985 IFB ISSUED IF8 No.: RS-0!E-86-171
Title:
" Graphic Services"
==
Description:==
Provide graphic / photographic services to the Technical Training Center in support of inspector training manuals, classroom displays, and other visual material.
Period of Performance: 2 years Sponsor: Office of Inspection and Enforcement Status:
IF8 issued on September 26, 1985. Bids due on October 25, 1985.
RFP ISSUED RFP No.: RS-RG5-86-331
Title:
" Radiation Monitoring Instrumentation Quality Assurance Program"
==
Description:==
The purpose of this project is to provide a fully implemented quality assurance program for an extensive inventory of d
instrumentation which includes scintillation detectors, ionization chambers, multi-channel analyzers and neutron detectors; and to assure a constant state of readiness for equipment dedicated for emergency response. The contractor shall possess a background in radiation protection technology, knowledge of nuclear counting procedures and a background in the practical and theoretical operating characteristics of a variety of radiation measuring instruments.
.. Period of Performance:
1 year with one year option Sponsor: Region V Status: RFP issued on September 24, 1985.
Proposals due October 24, 1985.
RFP No.: RS-0IE-86-170
Title:
" Technical Assistance for Emergency Response"
==
Description:==
The purpose of this project is to provide technical, logistical and administrative assistance for the maintenance and functioning of the NRC Headquarters Operations Center. The contractor shall provide technical, logistical and administrative support to the NRC's Headquarters Operations Center to fulfill exercise requirements and meet unanticipated needs that arise during normal operation or during an incident within a very short time span.
Period of Perfonnance:
1 year with 2 one-year options Sponsor: Office of Inspection and Enforcement Status:
RFP issued. August 20, 1985. Closing date has been extended by Amendment No. I to October 2, 1985.
I ENCLOSURE A SEP 2 71985
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o 4 PROPOSAL UNDER EVALUATION RFP No.: RS-0!E-85-167
Title:
" General Course in Non-Destructive Examination Technology and Codes"
==
Description:==
The purpose of this project is to provide NRC personnel the detailed technical training in nondestructive examination (NDE) and the applicable codes necessary to enable them to conduct in-depth inspection of NRC licensed facilities under construction or modification to determine whether or not such facilities and components are constructed properly in accordance with applicable codes and standards.
Period of Performance:
3 years Sponsor: Office of Inspection and Enforcement Status: RFP closed on September 16, 1985.
Proposals forwarded to Source Evaluators for review on September 20, 1985. Competitive range to' be established on October 31, 1985.
CONTRACTS AWARDED RFP No.: RG4-85-377
Title:
" Licensing Assistance in Geotechnical and Hydrological Evaluations"
==
Description:==
Technical assistance in the review of proposed tailings retention system and evaporation pond designs for confonnance to current NRC geotechnical and hydrologic criteria, and the preparation of Safety Evaluation Reports. Evaluation of long-term stability and isolation provided by proposed final tailings disposal and reclamation plans, including the evaluation of available engineering, design, operation and siting alternatives.
Period of Performance: 2 years Sponsor: Uranium Recovery Field Office, Region IV Status: Cost-Plus-Fixed-Fee / Task Order contract awarded to Goodson &
Associates, Inc. in the contract ceiling amount of $241,773.00 effective October 1, 1985.
RFP No.: RES-85-106
Title:
" Piedmont Seismic Reflection Study"
==
Description:==
Select a specific seismological problem related to the Southern piedmont, design a program of seismic reflection and other geophysical investigations, execute the program and interpret the resulting data. The information gathered is to be used to advance the state of knowledge on possible causes of seismicity in the Piedmont of Virginia and the Carolinas, particularly with respect to structure at hypocentral depths.
Period of Performance: 2 years with additional one-year option Sponsor: Office of Nuclear Regulatory Research Status: Cost-sharing type contract was awarded to Virginia Polytechnic Institute and State University in the amount of $776,075.00 effective October 1, 1985.
ENCLOSURE A SEP 2 71985 1
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. CONTRACTS AWARDED (Cont'd)
RFP No.: NMS-85-008
Title:
" Technical Assistance in Hydrogeology - Project A - Testing"
==
Description:==
The contractor shall provide technical assistance to the NRC in q
its review of DOE site investigation for a potential High Level Waste (HLW) geologic repository.
g Period of Performance: 2 years with 3 one-year options Sponsor: Office of Nuclear Material Safety and Safeguards Status:
Cost-Plus-Fixed-Fee type contract awarded to Williams & Associates, Inc. in the amount of $825,241.00 effective September 25, 1985.
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RFP No.: NMS-85-007 l
Titte: " Facility Systems Analysis Support"
==
Description:==
Provide technical support in the form of reports, analytical,
. and engineering expertise, to fully implement the regulatory effectiveness review program for all power plants.
2 Period of Performance: 24 months Sponsor: Office of Nuclear Material Safety and Safeguards Status: Cost-Plus-Fixed-Fee type contract awarded to Science Applications International Corporation in the amount of $583,260.00 effective September 25, 1985.
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ENCLOSURE A i
SEP 2 71985
i OFFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending September 27, 1985 Peach Bottom Atomic Power Station, Unit 3 On September 19, 1985, the NRC staff was informed by the Philadelphia Electric Company and General Electric by telecon that cracks had been identified at Peach Botton Unit 3 along both sides of the two 28-inch recirculation outlet safe end to pipe welds. The licensee indicates that these safe ends are composed of 316 L, low carbon (.019) material and have been in place since the beginning of commercial operation (1974).
In addition, there are no thermal sleeve attachments and, therefore, no creviced areas as previously reported in other safe end problems. The licensee is preparing to come to Bethesda to discuss these recent find.ings.
River Bend As of September 17, 1985, Gulf States Utilities has loaded 489 fuel bundles into the River Bend core. GSU is currently transferring the remaining 135 fuel bundles to be loaded into the core from the fuel building. Fuel loading should be complete by September 22, 1985, with initial criticality currently projected for September 30, 1985 to October 3, 1985.
River Bend received a low power license on August 29, 1985 and began loading fuel on August 31, 1985.
Palo Verde Unit 1 Palo Verde Unit I had an unscheduled shutdown on September 12, 1985.
During the staff's review, it was determined that the pressurizer auxiliary spray system was not safety grade as understood by the staff when the operating license was issued. The licensee agreed not to restart from a shutdown on September 16, 1985 until the design criteria -
for the auxiliary spray system was resolved to the satisfaction of the NRC staff. Region V issued a Confirmatory Action Letter on September 17, 1985 stating this commitment.
On September 20, 1985 the licensee met with the staff to provide more information including an indepth description of the sequence of events, design characteristics of the auxiliary spray system and proposed short term compensatory measures for continued operation. On the basis of the commitments made at the meeting, Region V issued a second Confirmatory Action Letter dated September 20, 1985, releasing the licensee from its commitment not to return Unit 1 to power.
The plant went critical Saturday, September 21, 1985 and is currently at 30%
1 power level.
ENCLOSURE B l
SEP 2 71985
Diablo Canyon - High Density Spent Fuel Storage By letter dated September 19, 1985, PG&E submitted a report describing high density spent fuel storage modifications for Diablo Canyon Units 1 and 2.
PG&E will submit the appropriate License Amendment Request in the near future. PG&E intends to install the new fuel storage racks in a dry spent fuel pool condition to reduce radiation exposure to plant personnel and to simplify overall installation work. The first refueling outage for Unit 1 could oc;ur as early as July 1986 (Unit 1 went commercial in May 1985).
The matter of high density spent fuel storage at Diablo Canyon has already received public attention in the San Luis Obispo area earlier this year. The City Council requested the California Legislature to hold exploratory public hearings. We will place the PG&E submittal into the Local Public Document Room and will initiate our review of the
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report. We will issue a Sholly Notice when the License Amendment Request has been Veceived.
Waterford 3 Louisiana Power & Light Company has announced that they placed their Waterford Steam Electric Station, Unit 3 into commercial operation on September 24, 1965. Waterford 3, which completed its Phase III Power Ascension Test Program on July 12, 1985, had been shut down for 68 days since July 18, 1985 for inspection, maintenance and repairs to its Westinghouse turbine generator. The plant is now on-line and supplying power to the grid.
D. C. Cook Gn September 17, 1985, the Indiana and Michigan Electric Company, the licensee, notified the NRC of their intent to request an extension of the environmental qualifications equipment for the D.C. Cook No. 2 beyond November 30, 1985. The licensee had been granted the November 30, 1985.
The licensee had been granted the November 30, 1985 date for several items and has since discovered a number-of other items for which qualification is questionable. They propose to operate an additional 30 full poder days beyond the November 30, 1985 deadline.
The licensee's full request is planned to be submitted prior to September 30, 1985.
D.C. Cook Unit 1 is shut down for the 10-year ISI.
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ENCLOSURE B SEP 2 71985 4
. Shoreham The licensee declared an unusual Event and commenced on unplanned reactor shutdown on September 25 when two ECCS systems became inoperable.
The HPCI turbine was inoperable for the performance of hot alignment checks, and the RHR system was being shutdown after being used for suppression pool cooling, when it discovered that the RHR pump bypass valve could not be shut. The RHR pump also serves as the LPCI pump.
The three inch bypass valve actuator was found to be separated from the valve body. The four actuator mounting bolts appeared to have sheared off. The licensee returned the HPCI turbine to service within about 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 15 minutes and stopped the reactor shutdown. The actuator failure is being investigated.
Browns Ferry Nuclear Power Plant, Units 1, 2 and 3 On September 25, 1985, Tennessee Valley Authority (TVA) declared all eight diesel generators at Browns Ferry manufactured by General Motors technically inoperable. The basis for this decision was twofold:
(1) it was found that some of the 3-year, 6-year and 12-year maintenance inspections (e.g., inspection of seals) recommended by the vendor had 1
not been performed and (2) a stud was broken while shimming the diesel generator battery racks, raising a question about seismic qualification i
of the racks.
All three units have been shutdown for sometime.
Unit 2 has been defueled since October 1984.
Unit 1 is defueled except for 50 assemblies and Unit 3 has been shutdown since March 19, 1985.
Based on preliminary information, TVA plans to inspect one or two of the diesel generators in consultation with the vendor.
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ENCLOSURE B SEP 2 71985
NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT WEEK ENDING SEPTEMBER 27, 1985 1.
PLANT STATUS The facility remains in long term cold shutdown with the Reactor Coolent 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 tilled
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with water to a depth of about 20 feet (about 5 teet 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 detueling platform is installed over the Internal Indexing Fixture in preparation for defueling.
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 70*F to 91 F with an average of 80'F.
Average cold leg temperature is 54*F.
The average reactor building temperature is 56*F.
ihe reactor building airborne activity is 9 8 E-7 uCi/cc Tritium and 1.9 E-10 uCi/cc particulate, predominantly Cesium 137.
2.
WASTE MANAGEMENT The Submerged Demineralizer System (505) was shutdown during this period.
EPICOR 11 completed processing batch 266 from Condensate Tank 1A (C0T-1A). To date 56,000 gallons from this batch have been processed. From September 26 to September 29, 1985 this water was transferred from CC-T-2 back to COT-1A. COT-1A had been deslodged in the interim while it was empty.
4 ENCLOSURE B SEP 2 71985
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Total volume processed through SDS to date is 2,963,375 gallons, and the total volume processed through EPICOR II is 2,662,982 gallons.
3.
DOSE REDUCTION / DECONTAMINATION ACTIVI1IES Decontamination activities are continuing on the 281' level of the auxiliary building.
Average general area radiation dose rate is 40 mrem per hour on the 347' level of the reactor building and is 67 mrem per hour on the 305' level of the reactor building.
4.
RADI0 CHEMISTRY ANALYSIS ERROR The licensee has identified an error at TMI-2 in their radiochemistry analysis procedure for quantifying strontium-90 (Sr-90) in solid samples. The error has resulted in samples being reported at one-half their actual Sr-90 values. The error does not affect gaseous or liquid samples since these are typically analyzed by a different process. The analysis error is believed unique to THI-2 in using a beta spectrometer for rapid assessment of accident-generated Sr-90 levels.
The error involved failure to correctly interpret calibration procedure wording with respect to equilibrium of Sr-90 and Yttrium-90 in the standards.
A prelim: nary evaluation by the licenses indicates the error is not likely to impact compliance with regulations related to occupational exposure or radiological effluent releases. The error does affect at least one past shipment of radioactive waste to U. S. Ecology in Hanford, Washington. The shipment documents indicate at least one barrel had not been accurately classified as required by State of Washington and NRC regulations (10 CFR 61.55).
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 Septeraber 7 through September 14, 1985.
The Lancaster water sample taken at the water works intake and analyzed by EPA consisted of a seven day composited sample taken from September 8 through September 14, 1985. A ganna scan detected no reactor related radioactivity.
The NRC outdoor airborne particulate sampler at the TMI Site collected a sample between September 18 and September 25, l'985. No reactor related radioactivity was detected. Analysis showed Iodine-131 and Cesium-137 concentrations to be less than the lower limits of detectability.
ENCLOSURE B SEP 2 71985
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6.
REACTOR BUILDING ACTIVITIES Defueling Water Cleanup System (DWCS) preoperational testing and modification continued.
Installation of cable troy shielding is complete.
Preoperational testing of the reactor building sump recirculation system components is complete.
The system is now operable.
Work is in progress on the canister positioning system and canister handling bridge.
Installation of the vacuum defueling system began.
7.
AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES Installation of the DWCS continued.
Partial DWCS turnover for processing RCS during early defueling is expected to be completed in e
October.
All four of the fuel canister storage racks have been delivered to the TMI site and inspected. The third rack delivered is being installed and its position adjusted in spent fuel pool "A".
The second' rack delivered has been repaired and re-inspected and is being prepared for installation. The first rack delivered has been i
repaired and is being re-inspected. The fourth rack is being repaired.
8.
NRC EVALUATIONS IN PROGRESS Technical Specification Change Requests numbers 48, 49, and 50.
Recovery Operations Plan Change numbers 29, 31, and 32.
Fuel Canister Technical Evaluation, Revision 1.
Defueling Safety Evaluation.
Application for seismic exemption.
SDS Technical Evaluation and System Description Update.
Core Stratification Sample Safety Evaluation.
Heavy Load Handling Safety Evaluation Report.
9.
PUBLIC MEETING The next meeting of the Advisory Panel is scheduled for October 16, 1985 in Lancaster, Pennsylvania at 7:00 PM. The meeting will be held in the Lancaster Council Chambers at 201 North Duke Street. Dr. H. Arnold Muller, Secretary, Department of Health will review the results of the Health Department's recently completed epidemiology studies.
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.
EHCLOSURE B SEP 2 71985
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OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending September 27, 1985 Near-Term NRC Actions Under the NWPA Section:
121(a) of NWPA:
EPA Final High-Level Waste Standards Action:
EPA final rule for Environmental Standards for the Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic
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Radioactive Waste (40 CFR Part 191) was published in the Federal Register (vol. 50, No. 182, p. 38066) on Thursday, September 19, 1985.
Status:
EPA Standards will be effective November 16, 1985.
Staff will review the NRC's high-level waste criteria for conformance with EPA standards and will provide a proposed rule to the Commission in 1985.
Section:
134 of NWPA:
Final Rule on Hybrid Hearings Action:
The Commission voted to approve the final rule establishing procedures for expansion of onsite spent fuel storage capacity or transshipment of fuel on September 5, 1985.
Status:
Staff has received the staff requirements memo and the final edited version is due to SECY on October 7, 1985.
Section:
114(e) of NWPA:
Project Decision Schedule Comments Action:
DOE had requested comments on the draft Project Decision Schedule by September 13, 1985, (SECY 85-282).
Status:
The Commission has voted to approve the comments with changes.
SECY expects the Commission to submit the comments to DOE by September 30, 1985.
Section:
301 of NWPA:
DOE Mission Plan Action:
NRC testified before Senate and House committees concerning the Mission Plan on Thursday and Friday, September 12 and 13,'1985.
Status:
NRC has been requested to testify concerning the Mission Plan and other high-level radioactive waste topics before the Senate Subcommittee on Nuclear Regulation (Simpson) on October 29, 1985.
ENCLOSURE C SEP 2 71985
. EPA Standards for Radon Emissions from Active Uranium Mills In a Federal Register notice on Wednesday, October 31, 1984, EPA issued an advance notice of proposed rulemaking (ANPRM) for setting standards to control radon releases from licensed uranium mills during operations.
These releases are now addressed in NRC and EPA rules as releases to be kept ALARA.
The new EPA standards will be issued under Section 112 of the Clean Air Act, not the Atomic Energy Act, as amended.
The driving force for prompt action is an agreement filed with the U. S. District Court for the Northern District of California.
The agreement was negotiated with the Sierra Club and filed with the court to avert suit by the Sierra Club.
EPA outlined their present plan at an informal meeting with NRC staff Monday, September 23, 1985.
EPA plans to issue a work practices standard and prescribe different standards for existing and new facilities.
EPA's schedule is to issue proposed rules in January, 1986, hold hearings in February, and issue final rules by May 1, 1986.
NRC described current practices at the sites to control radon releases during operation and encouraged flexibility in whatever standards are issued.
Staff members of both agencies agreed that continued interaction on the rule-making was desirable.
NFS-Erwin Strike by OCAW members continues.
NFS is conducting limited operations of the HEU production, scrap recovery and R&D facilities.
No problems with operations have arisen to date.
NRDC Hearing A memorandum to the Commission is in concurrence requesting that the NROC Hearing concerning NFS-Erwin be terminated, since the licensee has met all of the requirements stipulated in the 1983 Joint Agreement.
This final action has been concurred in by ELD.
Sequoyah Fuel Corporation Materials License 508-1010 for Sequoyah Fuels Corporation was renewed on September 20, 1985, for a 5 year term expiring September 30, 1990.
This action followed preparation of a Safety Evaluation Report, an Environmental Assessment (NUREG-1157), and publication of a " Finding of No Significant Impact" in the Federal Register on September 13, 1985.
The license autt.orizes Sequoyah Fuels to receive, sample, and convert yellowcake to uranium I
hexafluoride.
ENCLOSURE C l
i SEP 2 71985
, Trip to Wood County, West Virginia and Canonsburg, Pennsylvania A FC staff member visited the AMAX Inc., site in Wood County, West Virginia to observe the condition of the stabilized site and then attend meetings at Canonsburg, Pennsylvania, with representatives of DOE to discuss site certification and to tour the Canonsburg site.
The Canonsburg site remedial i
action will be completed in November 1985 and will be the first DOE UMTRCA Title I site to be completed.
l 4
l I
a
{-
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1 I
j 1
a 4
1 i
f ENCLOSURE C SEP 2 71985
OFFICE OF INSPECTION AND ENFORCEMENT Items of Interest Week Ending September 27, 1985 1.
The following Significant Enforcement Actions were taken during the past week:
a.
EN 85-64, a Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $100,000 was issued September 25, 1985 to Arrerican Electric Power Service Corporation (D.C. Cook Units 1 & 2).
This action is based on multiple examples of failure to maintain adequate control over access to vital areas, and a reporting viola-tion.
a b.
EN 85-65, a Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $50,000 was issued September 26, 1985 to
_ Sacramento Municipal Utility District (Rancho Seco). This action is '
based on violations of 10 CFR Part 50, Appendix B relating to seismic supports for the nitrogen supply and vent header system which connects to the reactor coolant system vent on the high point of the "B" hot leg. The lack of adequate supports resulted in a 17 gpm non-isolable primary coolant leak on June 23, 1985.
c.
EN 85-66, a Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $50,000 was issued September 26, 1985 to Baltimore Gas and Electric (Calvert Cliffs Units 1 & 2). This action is based on the licensee's failure to implement and maintain the installed upgraded post-accident sampling system.
2.-
The following IE Preliminary Notifications were issued during the past 4
week:
a.
PNO-TMI-85-09, GPU Nuclear Corporatin (TMI Unit 2), Radiochemistry Analysis Error, b.
PN0-I-85-66A, GPU Nuclear Corporation (TMI Unit 1), Fire in Control Rod Distribution Panels (Update).
c.
PNC-I-85-67,GPUNuclearCorporation(TMIUnit1),ReactorProtection System Breaker Malfunction.
i d.
PN0-I-85-68, Philadelphia Electric Company (Peach Bottom Units ? 6 3), Missing Employee.
e.
PNO-I-85-69, U.S. Department of Corrinerce, NOAA, NMFS, NEFC, Sandy Hooks Facility (Highlands, NJ), Fire Involving 75 Millicuries of Carbon-14.
f.
PNO-I-85-70, Long Island Lighting Company (Shoreham), HPCI and FHRB Out Of Service Concurrently.
ENCLOSURE D SEP 2 71985
. PNO-II-85-90, Duke Power company (McGuire Units 1 & 2), Fal.se Bomb g.
Threat.
h.
PNO-II-85-91, Carolina Power and Light Company (Brunswick Units 1 &
2), Actions in Response to Hurricane Gloria.
i.
PNO-II-85-92, Carolina Power and Light Company (Brunswick Units 1 &
2); Virginia Electric and Power Company (Surry Units 1 & 2); General Electric Company Nuclear Manufacturing Department (Wilmington, NC),
Actions in Response to Hurricane Gloria.
J.
PNO-III-85-84, Commonwealth Edison Company (Dresden Unit 3), Shutdown to Repair Scram Discharge Solenoid Valves, Maintenance.
a k.
PNO-III-85-85, Northern States Power Company (Monticello), Bomb
~
Threat.
r 1.
PN0-III-85-86, Toledo Edison Company (Davis-Besse), Main Steam Safety i
Valve Failure.
1 PNO-V-85-62, Southern California Edison Company (San Onofre Unit 1),
m.
Reactor Trip Involving Inoperable Turbine-Driven Auxiliary Feedwater Pump and Main Turbine Overspeed.
PN0-V-85-62A, Southern California Edison Company (San Onofre Unit 2),
n.
Reactor Trip Involving Inoperable Turbine-Driven Auxiliary Feedwater Pump and Main Turbine Overspeed (Update).
PNO-V-85-62B, Southern California Edison Company (San Onofre Unit 1),
o.
Second Update--Reactor Trip Involving Inoperable Turbine-Driven Auxiliary Feed Pump and Main Turbine Overspeed.
p.
PNO-V-85-63, Portland General Electric Company (Trojan), Reactor Trip and Subsequent Shutdown for Greater Than 48 Hours.
3.
The following IE Information Notices were issued during the past week:
IE Information Notice 85-77, Possible Loss of Emergency Notification a.
System Due to Loss of AC Power was issued September 20, 1985 to all holders of a nuclear power plant operating license or construction permit.
b.
IE Information Notice 85-78, Event Notification was issued September 23, 1985 to all nuclear power reactor facilities holding an operating license or a construction permit.
ENCLOSURE D SEP 2 71985
x r 4.
Other Items a.
Senior Management Meeting Deputy Director, IE, and Chief, Reactor Construction Programs Branch, Division of Inspection Programs were in Region II September 25, 1985 to meet with Region II, TVA, and QTC repre-sentatives concerning welding and recertification iss'as at Watts Bar.
b.
Enforcement Conference Director of Enforcement Staff and a member were in Region II c
for enforcement conferences on Vogtle, North Anna, Surry, and Tampa VA Hospital September 25, 26, 1985.
c.
Meeting-on Seabrook Director, Division of Emergency Prer.cedness and Engineering Response attended a meeting with Public Service New Hampshire -
Seabrook 1 & 2 on September 27, 1985.
d.
Civil Penalties Paid (1) On September 20, 1985 payment in the amount of $500 was received from Kay-Ray, Inc. (Arlington, Heights, IL) for i
enforcement action (EA 85-96) relating to a violation involving overexposure to a licensee employee.
(2) On September 23, 1985 payment in the amount of $21,425 was received from Omaha Public Power District (Fort Calhoun) for enforcement action (EA 84-122) relating to violations concerning access control to protected and vital areas.
e.
Incident Response (1) The Chief, Incident Response Branch and staff members, Division of Emergency Preparedness and Engineering Response attended a meeting on September 24, 1985 with ORM contractor 4
to discuss modifications to the existing Information Manage-ment System and conceptual design of upgrades to this system.
(2) The Chief, Incident Response Branch conducted a tour of the NRC Operations Center on September 26, 1985 for management representatives from Florida Power and Light. This tour discussad the agency's incident response program.
ENCLOSURE D
. f.
Events Analysis Representative of the Events Analysis Branch, Division of Emergency Preparedness and Engineering Response was at Dresden Unit 3 to support the followup of the September 19 event involving release of reactor water outside the drywell apparently because of problems related to the scram solenoid valves.
g.
Relocation Tabletop Exercise On September 26, 1985, a Relocation Tabletop Exercise working group session was held. Participants included members from the Incident Response Branch, Division of Emergency Preparedness and Engineering
_ Response, FEMA and their contractor, EPA and 00E.
h.
Vendor Program An inspection was conducted by the Vendor Program Branch, Division of Quality Assurance, Vendor, and Technical Training Programs, at San Onofre Units 1, 2, and 3 this week. This is one of a series of pilot inspections to review licensee equipment qualification program imple-mentation as required by 10 CFR 50.49.
1.
Steam Binding of Auxiliary Feedwater Pumps Representatives of Engineering and Communications Branch, Division
,~
of Emergency Preparedness and Engineering Response presented pro-1 posed IE Bulletin 85-XX on Steam Binding of Auxiliary Feedwater Pumps to CRGR on September 25, 1985.
j.
Notification on Undervoltage UV Trip Breakers NRC Headquarters received written notification dated September 13, 1985 from General Electric this week that a defect may exist on Undervoltage (UV) Trip Devices supplied for use on AK and AKR type Low-Voltage Power Circuit Breakers. A limited number of UV trip devices have recently failed to trip the circuit breakers when power was removed from the devices. Two types of defects were noted.
First, devices made between mid-1978 and May 1985 may have mating surfaces of armatures and pole pieces improperly painted. This paint may soften and stick to the pole piece causing failure to trip when power is removed.
In the second defect, UV trip devices were manu-factured with insufficient clearance between the armatures and the device r.ounting studs. Those licensees mentioned in the letter are:
Duke Power, GPU Nuclear, Arnansas Power and Light, Florida. Power Corporation, TVA, Maine Yankee, Northeast Nuclear, Baltimore Gas and Electric, Florida Power and Light, Louisiana Power and Light, Sacramento Municipal, Southern California Edison, and Arizona Public Service.
Except for Palo Verde, UV devices possibly having these defects were sold by GE only as replacement components in safety-related applica-tions. Many licensees mentioned use these devices as an essential SEP 2 71985 ENCLOSURE D
t
. element in the reactor trip system. GE expects to notify each potential user by September 23, 1985 tic Service Advice. Corrective action is to replace the UV trip davices showing either defect.
k.
Testing of Structural Welds Representatives of Engineering and Generic Communications Branch, Division of Emergency Preparedne';s and Engineering Response were at Franklin Research Center, Philadelphia, PA this week to review progress of Task M-210 concerning testing of structural welds.
1.
Foreign Visitor a
A representative from the Phillipines (sponsored by the IAEA) observed j
an emergency preparedness exercise at Ginna this week.
i e,
O e
ENCLOSURE D SEP 2 71985 t
1
0FFICE OF NUCLEAR REGULATORY RESEARCH Items of Interest Week Ending September 27, 1985 ROSA-IV The ROSA-IV system has recently performer 1 large-scale thennal hydraulic tests under a cooperative program with NRC. Test results are used to verify scaling parameters in NRC regulatory safety analysis codes.
A Program Review Meeting will be held on October 18, 1985 at 9:00 a.m. in the lith Floor Conference Room of the Willste Building. The primary objectives of this meeting are to:
(1) review the status of the ROSA-IV program, (2) review the Semiscale S-LH-1 test results, (3) coment on the proposed Semiscale S-LH-1 counterpart test to be conducted in the ROSA-IV 4
Large-Scale Test Facility (LSTF), (4) discuss the ROSA-IV data tape format and the schedule of transferring the tape to the USNRC contractors, Los l
Alamos National Laboratory (LANL) and EG&G Idaho, Incorporated (EG&G), and I
(5) review and comment on the proposed LSTF test candidates in FY 1986.
International Code Assessment and Applications Program (ICAP)
A review of the ICAP program was conducted with LANL, Sandia National Laboratory (SNL), and the Idaho National Engineering Laboratory (INEL).
" Procedures are currently under development for quantifying tne uncertainty of the TRAC-PWR, RELAP5, and TRAC-BWR codes. Assessments conducted to date have been mainly qualite.tive in nature. The quantitative assessment is expected to provide enginee-ing values for bias (if any) and confidence intervals for the codes. The efaluation will include important parameters (e.g., pressure, temperature, flow rate) for the principal classes of transients (large-break loss-of-coolant accident (LOCA), small-break LOCA, and transients). A procedure is being evaluated that provides a cias and uncertainty of the code as a function of time over the course of an individual transient. The results of all the transients for which the code was assessed are then combined to give the overall bias and uncertainty of the code. The methodology is being applied to previously i
conducted RELAP5/M001 and TRAC-BD1 assessment results to quantify these versions and to assist in developing final procedures. Since the task of quantifying the codes is complex and has not previously been perfonned, the development of the methodology is expected to require about one year with the work having begun in the Spring 1985.
Procedures have been established at LANL and INEL for the management and perfonnance of the ICAP program.
It is expected that assessment results and experimental data will be provided by more than ten countries. A quarterly newsletter has been started for each code.
EUCLOSURE E SEP 2 71985 l
l
i.
h.
. CONTAINMENT AEROSOL EXPERIMENTS Aerosol behavior in containment under post accident conditions has an important effect on any released fission products.
Large aerosol particles and sphere like agglomerates rapidly fall out of the containment atmosphere and the fission products released in the event containment fails would be lower than before the fallout. However, aerosols with a chain like agglomerate structure fall out more slowly.
From previous tests it is known that relative humidity has an effect on the aerosol's structure.
Chain like agglomerates are found with relative humidity levels of 20% or less. Sphere like agglomerates are found with the relative humidity levels at 100%.
In two recent tests successfully conducted by ORNL for iron aerosol, at 57% and 83% relative humidity, the results were chain like agglomerates.
Further tests, at higher levels of relative humidity, will be conducted in the Aerosol Moisture Interaction Test Vessel to determine the relative humidity at which the transition from_ a chainlike form to a spherical form takes place. This work is part of an effort to validate existing analytical models and codes which can accurately predict the post accident behavior of LWR aerosols within containment. The results will enable plant specific assessments of containment environments after accidents to establish equipment qualification requirements.
HYDR 0 GEN The potential for hydrogen to collect in local regions in detonable concentrations has been a safety concern for large dry PWR containments. A draft of a study has been completed that shows detonable mixtures in any portion of the large dry containment to be very unlikely. The study utilized HECTR in which the calculational volume elements are each "well mixed."
Comments on the draft noted that hydrogen stratification within the volume elements could exist. Furthermore a test in the FLAME facility at SNL, in which mixing fans were not used, resulted in a hydrogen concentration gradient of 10 to 15% from the bottom to the top of the facility at the end of 30 minutes. A study of the FLAME facility geometry with the detailed 3-dimensional HMS code, that includes diffusion and convection models, has shown excellent agreement with the hydrogen gradient results at the FLAME facility. The HMS code was then applied to representative volumes with various hydrogen stratifications imposed as initial conditions. The mixing is very rapid, even with initial stratification. Thus, the HECTR lumped parameter computations appear to be valid for the study of potential detonable concen-trations.
Further detailed calculations with HMS are expected to confirm the conclusions reached in the HECTR study that, even with 75% of the cladding reacting as provided by the Hydrogen Control rule, large dry PWR c.ontainments will not contain significant pockets of detonable hydrogen.
ENCLOSURE E SEP 2 71985 l
t
! Sodrce Term Code Package The stand-alone codes of the Battelle Suite of codes (see BMI-2104 and NUREG-0956) have now been combined to form the Source Term Code Package.
Minor modifications have been made to the codes in response to the peer review process, and the individual codes have been coupled in a consistent manner to the extent practical. Major portions of the code package have recently been taken to Brookhaven National Laboratory, where they are now being run and subjected to a quality assurance audit. The first set of plant analyses with the code package have been completed at BNL and now are undergoing audit. Additional analyses with the code package are being performed for the DRA0/RES risk y
rebaselining program.
Iodine Chemistry Workshop Dana Powers from Sandia and Ed Beahm from Oak Ridge attended the Iodine Chemistry Workshop at Harwell, United Kingdom on September 8-13, 1985.
The topics of discussion included the thermal chemistry of iodine in aqueous solution, radiation effects on the aqueous chemistry of iodine and reactions of iodine with organic materials to form organo-iodine compounds. The aqueous thermal chemistry of iodine was thoroughly studied and sophisticated kinetic models have been developed. On the effect of radiation on aqueous iodine chemistry, it was generally recognized that the effect is important but may be reduced if contaminants such as those found in the sump of TMI-2 are present. As for organic fodides formation, experimental evidence seems to indicate their origin is in irradiated aqueous solutions. The impact of these findings on severe accident source terms is that irradiated water pools may be important sources of volatile fodides.
ENCLOSURE E SEP 2 71985 i
D Meeting of the " Coordinating Committee for Low Level Waste Technologies" RES staff participated in the third quarterly meeting of the " Coordinating Comittee for Low Level Waste Technologies" in Las Vegas, Nevada, on Monday, Sept. 9, 1985. Attending were representatives of DOE, EPA and NRC; the States of Texas Illinois, Pennsylvania, New York, and the Southern States Energy Board which represents 16 other states and Puerto Rico; as well as industry representatives such as EPRI, RAE, and EG&G.
This comittee was established for the purpose of assuring that technological information is developed without duplication and that it is transferred to those who could use it in a timely
- fashion, This meeting illustrated that the process is working. An example is that EPRI e
is developing an " Alternative Disposal Technological Definitions" system that is intended to provide a standard nonmenclature for the various components of' all LLW disposal systems.
EPRI had asked the Comittee to review this effort and it was discussed at previous meetings.
This EPRI system of nonmenclature is being used in a research project being conducted by EG&G Idaho for RES on Safety Assessment of Alternatives to Shallow Land Burial. This project is developing a quantitative method for ranking the relative importance of each design component of LLW disposal systems and an evaluation methodology that could be used to compare the importance to safety of particular engineered fractures and the merits of various alternative disposal systems. A progress report on this program was presented at this meeting by EG&G, and discussion on it took up most of the meeting.
State representatives on the Committee expressed the view that the methodology shows promise in helping them to assess and select disposal systems for their States.
International Symposium on Coupled Processes in HLW Disposal On September 18, 19, and 20, 1985, an " International Symposium on Coupled Processes Affecting the Performance of a Nuclear Waste Repository" was held at the Lawrence Berkeley Laboratory in Berkeley, CA. " Coupled Processes" is the term used to describe the complex interactions among the therral, mechanical, chemical, and hydrological phenomona that characterize the behavior of a geologic repository. The symposium was funded by NRC and the Department of Energy, and nonfinancial sponsorship was provided by the OECD Nuclear Energy Agency and the Comission of European Communities. The original motivation for the symposium was provided by the activities of the NRC HLW rese, arch project " Investigation of Coupled Interactions in Geothermal and Hydrothermal Systems for the Assessment of HLW Isolation." The purpose ENCLOSURE E SEP 2 71985
. of the symposium was to bring together U. S. workers and workers from other countries to discuss recent results of field, laboratory, and theoretical studies of coupled thermal, hydrologic, mechanical, and chemical interactions relevant to the geologic disposal of HLW.
Selected researchers working in HLW test facilities abroad were invited to present their experiences on how best to study coupled processes in field test facilities and how sensitivity studies might be conducted for field test designs. The discussion centered around identifying and characterizing the significance of coupled processes for HLW isolation, assessing the current state of knowledge of coupled processes, and considering how to address coupled processes from the perspective of workers who are investigating coupled processes for HLW applications.
The final version of the proceedings of the symposium will be printed as a NUREG/CP document and will be published in a hardbound volume prepared by the Academic Press.
r International Works' hop on Radiation Embrittlement Mechanisms
~
NRC RES staff and contractors participated in an international worksh,p on mechanisms of radiation embrittlement of LWR pressure vessel steel at Monterey, California, September 12-14, 1985. The workshop was organized by NRC and EPRI contractors, and included attendees from the U.K., FRG, Finland, and U.S. representatives from national laboratories, universities, reactor operators and manufacturers. Most of the scientists actively working on determining the fundamental aspects of neutron radiation embrittlement were present. The development of such information is very important in predicting quantitatively the property changes used in the pressurized thermal shock evaluation, and for reactor
' vessel heatup and cooldown curve predictions.
It will become even more necessary for the issue of plant life extension because embrittlement information will be very limited for the vessel materials that might be annealed and reirradiated.
The objectives of the workshop were to (1) carry out a critical review of the current. understanding)of embrittlement mechanisms, annealing and reirradiation effects, (2 identify experinents and techniques needed to resolve key questions, and (3) define potential areas of interaction and collaboration between the various research groups, including comon material bases, joint irradiations and round-robin benchmark experiments.
Various new tools for observing fine-scale microstructural changes wrought by irradiation, including small angle neutron scattering, positron annihilation and others, were discussed in detail; it appears that these approaches can effect very significant improvenent in our understanding of the basic causes of the degradation of mechanica1 properties in pressure vessel steels due to radiation. Coordinated experiments are being planned to use well characterized materials, for the purpose of cross-comparison of techniques to track down what irradiation does to nicrostructure. The group is developing correspcndence links, and hopes to meet again in approximately a year to establish a more formal organization for the exchange of research results and for ENCLOSURE E coordination and integration of research activities.
SEP 2 71985
. RES Rulemaking Activities Appendix K:
The regulatory guide associated with the rule was distributed for Office review and comment on July 24. A revised Federal Register notice incorporating changes based on DRR, ELD, NRR, CRGR and RES comments accom-panied the regulatory guide. Because of difficulty in achieving consensus on the regulatory guide, current schedule estimates indicate Commission paper and regulatory guide to CRGR in December 1985; to Commission in January 1986, with the research report; and publication of NPRM by end of March.
Well-Logging Rule:
A second meeting to discuss public comments was held September 23 between S. McGuire, RES and B. Carrico and J. Brown, NMSS.
Training and paperwork requirements have emerged as the main issues and will
~
be considered as the final rule is developed. The rule will be discussed at, the Annual All Agreement State meeting in Bethesda on Oct. 9.
The issue of compatibility will be brought up.
A visit to a mineral and coal logging company in western Virginia is planned for about Oct. 16.
Risk Effectiveness of LWR Regulatory Requirements:
We have received two draf t reports from PNL:
(1) Identification of Regulatory Requirements that have Marginal Importance to Risk, and (2) Assessment of Selected Regulatory Requirements that may have Marginal Importance to Risk.
Both reports were forwarded for staff review and comment (due 9/25/85). A meeting is scheduled on 10/3/85 to discuss comments on the two draft reports.
We also completed a preliminary draft of a staff recommendation to the ED0 on reactor containment leakage rate and leakage testing.
The draft was also
' distributed for staff review and comment (due 9/30/85).
Recently Issued Publications R. G.1.34, Rev. 23 - Design and Fabrication Code Case Acceptability ASME Section III, Division 1 R. G.1.85, Rev. 23 - Materials Code Case Acceptability ASME Section III, Division 1 R. G.-1.147, Rev. 4 - Inservict Inspection Code Case Acceptability ASME Section XI, Division 1 Draft Regulatory Guide and Value/ Impact Statement: Onsite Meteoro' logical Measurement Program for Uranium Recovery Facilities - Data Acquisition and Reporting, Task ES 401-4. Comments requested by December 2,1985.
Contact:
L. Brown (301) 427-4628.
ErlCLOSURE E SEP 2 71985
ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING SEPTEMBER 27, 1985 Interagency Task Force Meeting On September 26 the Interagency Task Force for Nuclear Exports held their monthly meeting to discuss highlights since the last meeting. A i
briefing was given by some Task Force members regarding their recent visit to Yugoslavia and the Netherlands and nuclear power developments in those two countries. Discussions were also held regarding the proposed U.S. Government Industry Seminar / Workshop to be held in the
~-
People's Republic of China in the spring of 1986. The Seminar / Workshop would be similar to those which were held in Portugal and Yugoslavia.
International Visitors On Monday Professor M. P. Singh, Head of the Centre for Atmospheric and Fluids Sciences of the Indian Institute of Technology, met with RES staff members to discuss the development of computer models for the dispersion of atmospheric pollutants as a result of industrial accidents.
i I
A i
ENCLOSURE G l
SEP 2 71985 t
1
t 0FFICE OF STATE PROGRAMS ITEMS OF INTEREST WEEK ENDING SEPTEMBER 27, 1985 Northeast Low-Level Waste Compact On Thursday, September 19, 1985 the Northeast Interstate Low-Level Radioactive Waste Compact was introduced into the U.S. House of Representatives as H.R. 3372.
The Compact members include Connecticut, Delaware, Maryland and New Jersey. Washington, DC has also petitioned to join the Compact.
Review of Colorado Program A review of the Colorado radiation control program will be performed October 14-25, 1985.
ENCLOSURE H
$dP 2 't 1985
OFFICE OF RESOURCE MANAGEMENT Items of Interest Week Ending September 27, 1985 ADP Steering Group A briefing on the Corporate Data Network (CDN) Strategic Data Plan was presented to the ADP Steering Group by Touche Ross and Company on September 23, 1985. The Office of Resource Management also provided the Steering Group with a briefing on their plans for CDN development and current efforts to prototype two of the databases (Unit and Event) covered in the CDN e
Strategic Data Plan. Based on these briefings the Steering Group approved RM's plans to proceed with these activities.
Revised NRC Manual Chapter 4125 Revised NRC Manual Chapter 4125, Differing Professional Opinions, was issued to all NRC employees. The revision incorporates recommendations by a special review panel and the Office of Inspector and Auditor.
FY 1986 Funding H.J. Res. 388 passed the Congress on September 25, 1985, which provides for FY 1986 continuing appropriations for the period October 1, 1985 through November 14, 1985. Prepared request to the Department of Treasury for our Appropriation Warrant to continue operating during the Continuing Resolution, and prepared the Apportionment Schedule for 0MB to provide funding for the first 45 days of FY 1986.
Limited Cash Reimbursement for Local Travel at H Street Effective October 1,1985, H Street employees will be able to obtain cash reimbursement for local travel expenses of less than $10.00 from the H Street subcashier(ADM).
ENCLOSURE I SEP 2 71985
REGION III STATUS REPORT DAVIS-BESSE LOSS OF FEEDWATER EVENT SEPTEMBER 30, 1985 Plant Status The plant remains in cold shutdown. The circulating water canal is drained.
Decay heat removal loop No. 1 is drained for maintenance.
ENCLOSURE L SEP 2 71985
yA. EQUIPMENT STATUS (FOLLOWS TABLE 5.1 IN NUREG 1154) p
'u'
[
TROUBLESP00 TING /R00T CAUSE RIII ACTIONS ITEM DETERMINATION ACTIVITIES, COMMENTS g
1.
Main Feedwater Cause determined to be component MFPs were tested on 09/05-Region III is monitoring Turbine failure in speed control circuit.
06/85 with noiproblems noted.
licensee evaluation of reliability of the MFPs.
Revised report. issued 08/30/85.
2.
Closure of MSIVs Cause determined to be that circuit Testing will continue through RIII monitoring licensee's was overly sensitive to momentary next week. Specialist from activities and observing system perturbation. Revised NRR will: observe testing as selected activities.
report issued 09/07/85. Additional required.
root cause detenninations are continuing.
3.
Steam Safeties,**
Defective electronic module in Seven of Eight MSSVs shipped RIII folicwing licensee Atmos. Vents.
ICS likely cause of problem with to Wylie for full flow steam activities.
atmospheric ve 4 valves. Revised testing and internal inspec-report issued 09/06/85. MSSVs tion failed. The seven are being evalcated.
being reset by the manufacturer.
Ten additional MSSVs are being removed and tested onsite.
4.
Aux. Feedwater Turbine Cause considered to be condensation Preparations are being made to RIII inspectors to in long steam inlet lines. Revised modify the steam supply system.
observe activities.
report issued 09/09/85.
Governor from #2 AFWPT has been removed and sent to Woodward along with two spare governors for inspection and modifications.
Governor for #1 AFWPT has been replaced with a new type governor.
5.
AFW Containment Completed and revised report issued Additional dp and flow testing RIII following licensee's Isolation Valves 08/29/85. Misadjustment of bypass is being evaluated.
activities.
torque switch settings and inadequate testing procedure.
6.
Steam Supply Valve No cause was identified. Revised Activities completed.
RIII to observe any to AFPT No. I report issued 09/09/85.
Additional testing additional testing.
is planned in hot standby.
- =
E 2
o
. TROUBLESHOOTING / ROOT CAUSIP o
m
$1 TEM DETERMINATION ACTIVITIES COPMENTS RIII ACTIONS u,
-37. Source Range NI Revised report issued 09/16/85 Licensee is considering RIII observing activities.
Q on NI-1.
Root cause was bad replacing the containment cable connection between detector and penetration modules. NI-1 is m
cable.
being monitored and appears stable.
8.
PORV Completed and report sent to NRR Valve will be rebuilt (as RIII observing activities.
08/23/85. Root cause not deter-needed). Two spare PORVs are Vendor Programs Branch has mined.
being rebuilt at Crosby, and been notified.
will be' tested at Marshall Steam Station in Terrell, N.C.
in October.
9.
S/U Feedwater Control Completed and revised report issued Work complete.
None.
Valve 08/29/85. The valve functioned correctly during the June 9 event.
- 10. Recovery of AFP Completed and revised report issued Procedure has been revised and RIII to review operator Turbine 08/30/85. Training and procedural operator aids (instructions) training program to deficiencies identified, will be posted at the turbines.
assure proper operator actions.
- 11. AFP No. 1 Suction Revised report issued 09/17/85.
Individual pump suction RIII observing activities.
Transfer Root cause determined to be strainers will be removed and excessive pressure drop across the common suction strainer will common strainer caused by be replaced with a coarser mesh j
transient flow variations.
strainer.
- 12. Turbine Turning Gear *
- 13. Control Room HVAC*
- 14. Turbine Bypass Valve Completed and ravised report issued New drain header has been RIII to monitor.
08/29/85. Valve failure caused by installed. New valve operator water hammer.
has been shipped from vendor.
- Status not maintained on this item since these type failures occurred.previously and do not appear to be unique to this event.
- Show change in, status from previous update.
E P
3 8
15 m
I""
B. REGION III STAFF ACTIONS AS ASSIGNED BY W. DIRCKS ME p 0F AUGUST 9, 1985,,
9 Adequacy of the licensee's management and maintenance activities 1.ro Item:
STATUS / COMMENTS ACTION Region III, Davis Besse study group u,
(b) Evaluate and take action on the established to review LER's, DVR's licensee's response to findings (Deficiency Reports) and enforcement concerning management practices history and determine if licensee's and (e.g., control of maintenance Region III's actions were adequate and programs and post-trip reviews).
appropriate.
Inspections are ongoing.
Reliability of the AFW containment isolation valves and other safety-related valves 6.
Item:
STATUS /COPHENTS ACTION Region III inspection specialists from the (a) Monitor the licensee's trouble-Division of Engineering and the Resident shooting activities Inspectors are monitoring the licensee's troubleshooting activities.
(See Table A on Equipment Status.)
A Region III specialist is following the (e) Determine that the procedures for licensee's actions and has reviewed the adjustments of the AFW isolation licensee's procedures for adjustment of valves such as torque switch bypass torque switch bypass switches and torque switches are clear and proper, and switches. The licensee has purchased a that associated training programs M0 VATS machine to aid them in the setting are adequate. Confirm that adjustment of all limitorque operated valves.
settings are consistent with plant procedures.
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Item: Adequacy of emergency notifications c
STATUS / COMMENTS m
ACTION
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9 Region III Emergency Preparedness has (a) Verify the adequacy of the licensee's reviewed the licensee's training and m
procedures and training for the report-4
-Q ing of events to the NRC Operations procedures for reporting of events to the NRC. One violation of NRC requirements was found. Region III is reviewing the m
licensee's reporting per 10 CFR 50.72 and l
8.
Item: Reliability of AFW pump turbines STATUS / COMMENTS ACTION (a) Monitor the licensee's trouble-(See Table A.)
shooting activities including possible hot plant operation to 1
l confirm failure mode.
NRC testing review group consisting of IE, (d) Verify that the AFW system has been NRR, and Region III members established and adequately tested to confirm system will review AFW system testing.
configuration involved with design 4
basis events.
(e) Review the implementation of the A training assessment team inspection was completed on 9/26/85. Region III will operator training program to assure folicw the licensee corrective actions proper operator actions, such as relative to team findings.
resetting of trip throttle valve.
I 9.
Item: Reliability of the PORV STATUS / COMMENTS ACTION (a) Monitor the licensee's trouble-Troubleshooting complete. The ifcensee intends to rebuild the PORV and perform i
shooting activities bench testing prior to plant startup.
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STATUS / COMMENTS ACTION-u>
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. Monitor the licensee's trouble-(See Table A.)
(a) co shooting activities 5
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Other Activities The licensee stopped work 9/25/85 on all nuclear safety related work due to problems with control of vendor manuals.
Some work resumed on 9/27/85 after controlling procedures were modified and plant personnel were instructed on the proper use of vendor manuals.
The new electric motor driven startup feedwater pump (SUFP) is in place.
Installation of pipe and valves is about 70% complete. Conduit installation, cable pulling and wire termination is in progress. The old SUFP has been electrically disconnected.
Evaluations and inspections relating to the auxiliary feedwater system restraints are continuing. Baseline inspections of the No. 2 HPI and the No. 2 LPI systers are continuing. A hanger for the No. 2 HPI system was determined to be inoperable. The licensee is evaluating the effect of the inoperable hanger on the operability of the HPI system.
Eight additional licensee inspection teams have begun inspection of 800 pipe supports in containment.
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Nonconformance Reports (NCRs) have been written against 621 of the 652 pipe supports inspected so.far. Licensee's engineering department has received 509 '
NCRs for evaluation. To date, 160 NCRs have been dispositioned, fourteen require rework, none require welding.
Testing of motor operated valves by M0 VATS, Inc. has resumed. RIII specialist will be on site next week to review this program and witness testing.
Corrective Action Plans
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Corrective action plans to repair equipment that malfunctioned during the event have been issued for the following equipment items. Work is in pr6gress on most of the action plans.
Item numbers correspond to Table 5.1 in NUREG' 11,54.
ITEM PLAN DATE ISSUED 1.
Main Feedwater Turbine 4
08/26/85 6
09/03/85 2.
Closure of MSIVs 1
09/04/85 4.
Auxiliary Feedwater Turbine 1
09/20/85 (Rev. 1) 5.
AFW Containment Isolation Valves 1
09/07/85-(Rev. 1) 6.
Steam Supply Valve to AFPT No. 1 1
08/29/85 7.
Source Range NI-1 1/2 09/18/85 1
Source Range NI-2 1
09/23/85 8.
PORV 1
09/09/85 (Rev. 2)
ENCLOSURE L SEP 2 71985 7
P 9.
S/U Feedwater Control Valve 1
09/08/85 (Rev. 3) l l
- 10. Recovery of AFP Turbine 1
09/09/85
- 11. AFT No. 1 Suction Transfer 1
09/04/85 I
- 14. Turbine Bypass Valve 1
09/05/85 (Rev. 1) i 2
08/26/85 l
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The Davis-Besse Course of Action Report submitted on 09/09/85 is under review. A separate inspection plan is being developed based j
on this review.
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i ENCLOSURE L SEP 2 71985 j
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I ITEtts ADDRESSED BY THE C0t1 MISSION - WEEK ENDING SEPTEMBER 27, 1985 A.
SECY-85-302 - PROPOSED RETRANSFER FOR REPROCESSING (SWITZERLAND TO THE U.K.)'
SECY Memo to W. Dircks dated 9/23/85 This is to advise you that the Commission (with all Commissioners agreeing) has approved the proposed response to DOE.
The Office of International Programs was advised of this 1
action on September 20, 1985.
B.
STAFF REQUIREMENTS - AFFIRMATION / DISCUSSION AND V0TE, 11:30 A.M., THURSDAY, SEPTEMBER 5, 1985, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to W. J. Dircks and H. H. E. Plaine dated 9/23/85
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I.
SECY-85-242 - Mr. Husted's Request for Hearing
- The Commission, by a 5-0 vote, approved a notice of hearing which grants the request of Mr. Charles Husted for a hearing on the issue of whather the Appeal Board's condition barring him from supervisory responsibilities insofar as the training of non-licensed personnel is concerned should be vacated and on the related question of whether he is barred by concern about his attitude or integrity from serving as an NRC licensed operator, or a licensed operator instructor or training supervisor.
The notice of hearing instructs the Chief Judge of the Atomic
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Safety and Licensing Board Panel to appoint an Administrative Law Judge to preside over the hearing and authorizes the Atomic Safety and Licensing Appeal Board to exercise the authority and perform the review functions which would otherwise be exercised and performed by the Commission.
(Subsequently, on September 5, 1985 the Secretary signed the Notice of Hearing.)
II.
SECY-85-102B - Procedures to be Followed When a Subpoena or Other Demand for Disclosure of Records or Information is Served on NRC Employees The Commission, by a 5-0 vote, approved a final rule, the addition of Subpart D to 10 CFR Part 9 to prescribe procedures for production of documents or disclosure of information in response to subpoenas or demands of courts or other judicial authorities in State and Federal proceedings.
(Subsequently, on September 11, 1985 the Secretary signed the Federal Register Notice.)
- This item was previously issued separately 9/12/85 ENCLOSURE 0 SEP 2 71985
s -
B.
CONTINUED, III.
SECY-85-235 - Final 10 CFR Part 2, Subpart K,
" Hybrid Hearing Procedures for Expansions of Onsite Spent Fuel Storage Capacity at Civilian Power Reactors" The Commission, by a 5-0 vote, approved the issuance of a final l
rule establishing hybrid hearing procedures for licensing proceedings regarding expansion of spent nuclear fuel storage capacity at civilian nuclear power reactor sites.
The Commission also approved several modifications proposed by Commissioners Zech and Bernthal (as shown in the attached pages 16, 31, 33, 41, and 42).
Commissioner Asselstine preferred the original text of pages 16, 31, 33, and 42.
1 You should forward the Federal Register Notice as modified for signature and publication in the Federal Register.
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(EDO)
(SECY Suspense:
10/7/85)
Attachments: bei cacmed As stated C.
STAFF REQUIREMENTS - DISCUSSION ON EARTHQUAKES AND EMERGENCY PLANNING, 2:00 P.M.,
MONDAY, SEPTEMBER 9, 1985, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to W. il. Dircks and H. E. Plaine dated 9/24/85 The Commission met to discuss the draft " Proposed Amendments tc, 10 CFR Part 50, Appendix E; Consideration of Earthquakes in Emergency Planning" (SECY-85-283).
4 l
Mr. Richard Krimm of the Federal Emergency Management Agency was present and responded to several questions from the i
Commission.
The Commission requested the Office of the General Counsel to determine whether the public was given access to and opportunity i
to comment on the proposed rule package and to advise the I
Commission whether it will be necessary to resubmit the proposed rule for comment.
(OGC)
(SECY Suspense:
10/4/85)
The Commission also requested that the Office of the General Counsel provide comments on the alternative proposed in the j
September 6, 1985 memorandum from the Office of Policy Evaluation to the Commission.
(OGC)
(SECY Suspense:
10/4/85)
The Commission requested that Mr. Krimm of the Federal Emergency l
Management Agency submit FEMA's views on the proposed rule to l
the Commission.
l (EDO/R. Krimm)
I ENCLOSURE 0 I
SEP 2 71985
D.
STAFF REQUIREMENTS - DISCUSSION OF PLANT ISSUES WITH REGIONAL ADMINISTRATORS, 3:00 P.M., WEDNESDAY, SEPTEMBER 11, 1985, COMMISSIONERS' CONFERENCE ROOM, DC 0FFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to RECORD dated 9/24/85 The Commission met with Regional Administrators representing Regions I, II and III to discuss plant issues including con-struction and licensing agendas for plants under their juris-dictions and significant plant operating problems encountered by the regions.
The Administrators also advised the Commis-sion of management, personnel and operational changes in the regional offices.
There were no staff requirements at this meeting.
E.
STAFF REQUIREMENTS - STAFF BRIEFING ON TVA, 2:00 P.M., THURSDAY, SEPTEMBER 12, 1985, COMMISSIONERS' CONFERENCE ROOM, DC 0FFICE (OPEN TO PUBLIC ATTENDANCE)
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Memo SECY to RECORD dated 9/24/85 The Commission met with the staff for a briefing on the ef-forts of the Tennessee Valley Authority (TVA) to improve the management, operation and safety of the nuclear. power plants owned by the Authority or under construction for'TVA.
The Commission discussed the desirability of meeting with TVA at a later date and decided to reconsider the matter after the Commission has received the information which the staff is-requesting frcm TVA.
There were no requirements for the staff at this meeting.
M.
G ENCLOSURE 0 SEP 2 71985
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F.
STAFF REQUIREMENTS - CONTINUATION OF 7/24/ BRIEFING ON DAVIS-BESSE, 10:30 A.M.,
TUESDAY, SEPTEMBER 17, 1985, COMMISSIONERS' CONFERENCE ROOM, D.C. 0FFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to RECORD dated 9/24/85 2e Ccmnission discussed with representatives of Toledo Edison 'the actions of the licensee following the event of June 9,198S at the Davis-Besse plant which resulted in the loss of all feedwater.
S e following representatives of Toledo Edison were in attendzince at the meeting:
John P. Williamson Chairmm Joe Williams, Jr.
Senior Vice President - Nuclear Steve Smith Assistant Plant Manager, Maintenance John Wood Mechanical / Structural Engineering Manager Ted Myers Nuclear Safety and Licensing Director Sushil Jain Senior Nuclear Engineer Jacque Lingenfelter Operations Engineering Manager Bill O'Conrdr Ass'istant Plant Manager Operations Mel Ste%3rt Training Director No staff requirerents were issued following the Toledo Edison presentation.
ENCLOSURE O SEP 2 71985
STAFF REQUIREMENTS - DISCUSSION OF PROPOSED STATION BLACK 0UT RULE, 1:30 P.M.,
G.
WEDNESDAY, SEPTEMBER 11, 1985, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to RECORD dated 9/25/85 The Commission met with staff to discuss the " Proposed Station Blackout Rule" (SECY-8 5-16 3).
Chairman Palladino requested that Commissioners provide the staff with any questions they have related to the proposed rule.
(OCM)
Chairman Palladino indicated that a follow-on meeting would be scheduled at an upcoming agenda planning session.
(Subsequently, the Commission scheduled a follow-on meeting for Wednesday, October 9, 1985 at 2:00 p.m.).
STAFF RE0UIREMENTS - AFFIRMATION / DISCUSSION AND V0TE, 3:30 P.M., THURSDAY, H.
12, 1985, COM4ISS10NERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO SEPTEMBER PUBLIC ATTENDANCE) Memo SECY to W. Dircks and H. E. Plaine dated 9/25/85 SECY-85-286
" Exceptions" to Commission Order Establishing I. Information Hearing on Babcock and Wilcox Parks Township Facility The Commission, by a 5-0 vote, approved an order which denies a 1985 request that the Commission amend its July 24, July 30, 1985 Order that had referred a hearing request on B&W's Parks Township Facility to the ASLBP for consideration in an informal hearing, and asked for a formal hearing instead.
(Subsequently, on September 19, 1985 the Secretary signed the order.)
II.
SECY-85-287 - Review of ALAB-809 The Commission, by a 5-0 vote, approved an order that vacates ALAB-809 and the underlying Licensing Board decision as moot because the Licensing Board has subsequently completed its consideration of the Graterford emergency planning contentions.
(Subsequently, on September 19, 1985 the Secretary signed the order.)
SECY-85-150 - Final Policy Statement on Engineering III.
Expertise on Shift The Commission, by a vote of 4-1 (with Commissioner Roberts disagreeing), approved Version A of the Final Policy Statement on Engineering Expertise on Shift subject to the following:
i ENCLOSURE 0 SEP 2 71985
H.
CONTINUED 1.
Item b(1) (b) of Option 1 should be amended to read:
"A Professional Engineer's (PE) license obtained by successful completion of the PE examination."
(Chairman Palladino and Commissioners Bernthal and Asselstine agree.)
2.
Item b(1) (c) of Option 1 should be deleted.
(Chairman Palladino and Commissioners Bernthal and Zech agree.)
3.
Item b(1) (f) of Option 1 should be deleted.
(Chairman Palladino and Commissioners Bernthal and Zech agree.)
4.
Item b(2) of Option 1 should be deleted.
(Chairman
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Palladino and Commissioners Asselstine, Bernthal and Zech-agree.)
5.
The reference to 10 CFR 50.54 (m) (2) (1) should be corrected to 50.54 (m) (1) (i).
Commissioner Roberts prcvided additional comments (attached) to be included in the Federal Register Notice.
The Commission understands that the staff has given conditional approved to several licensee programs to combine the SRO/STA positions based upon the policy statement as submitted to the Commission in SECY-85-150.
If the approved policy statement will cause significant difficulties for these licensees, you
.. should so advise the Commission and indicate any actions to be taken to alleviate the situation.
A marked up copy of the modified policy statement is attached.
The suppletaentary information that accompanies the policy statement should be modified to be consistent with the agreed upon policy statement.
The revised Federal Register Notice should be returned for signature and publication in the Federal Register.
affected licensees.A copy of the policy statement should be sent to all You should also advise NUMARC of the commission's decision on the policy statement.
(EDO)
(SECY Suspense:
10/18/85)
Attachments: - Amt euetoged As stated SEP 2 71985 ENCLOSURE O
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to 2
NRR MEETING NOTICES
- SEPTEMBER 20, 1985 DOCKET APPI.ICANT/
DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT i
i 9/30/85 P-118 To discuss examiner requali-Boiling Water Reactor R. Hermann I
9:00 am Bethesda fication program, scope and Owners Group program of BWROG II on inter-granular stress corrosion 4
1 cracking research, and other technical issues related to IGSCC.
1 l
9/30/85 50-312 Rancho Seco Site Survey Adm. and Organ. of the Sacramento Mulicipal S. Miner in 10/4/85 Sacramento, Calif Maintenance and Surveillance Utility l
10/1/85 50-278 P-422 Peach Bottom Unit 3 - Safe-Philadelphia Elec.
G. Gears 1:00 pm Bethesda end cracks i
10/2/85 50-259 P-422 Discuss TVA's Integrated TVA R. Clark i
9:30 am 50-260 Bethesda Schedule for NRC-Required I
50-296 Modifications 10/2/85 50-443 Brookhaven Nat'l Discuss NRC review of the Public Service of V. Nerses 1:00 pm 50-444 Lab Seabrook Station Probabilistic of New Hampshire Brookhaven, L.I.
Safety Assessment 10/9/85 50-346 P-110 Discussion of Technical aspects Toledo Edison Co A. DeAgazio J
9:00 am Bethesda and implementation schedule for detailed control room design review at Davis-Besse f
10/9/85 50-219 Rm 5215 Discuss questions on info needed GPU Nuclear Corp J. Donohew l
9:30 an Air Rights III by staff to complete review of i
4550 Mont. Ave.
the Oyster Creek control room m
5 Bethesda within the Detailed Control Room j
{
Design Review NUREG-0737 Item I.D.I.
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NMSS MLETING NOTICES 1
FOR WEEK ENDING: 9/27485 l
M p
i Divisi::n of fuel Cycle cnd Material Safety m
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DOCKET ATTENDEES /
g DATE/ TIE NUPOER LOCATION
. PURPOSE APPLICANT NRC CONTACT
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I 9/30-10/2/85 Knoxville, To discuss with ORNL the environmental E. Shum (FC)
Shum TN assessment on NFS, SFC and Mallinck-M. Horn (FC) rodt, Inc.
Reps of ORNL 10/7-11/85
- Vienna, IAEA Advisory Group to prepare a D. Cool (FC)
Cool Austria Safety Series document on "The:
Application of the Principles of Radiation Protection to Sources of Potential Exposure, with Special Reference to Radioactive Waste Repositories."
10/8/85
- Paris, Working Group on Fuel Cycle Safety J. Roberts (FC)
Roberts (in connection w/ trip France meeting, Committee on Safety of to FRG on 10/1-4/85)
Nuclear Installations (CSNI).
10/7-9/85 Livermore, To discuss Modal Study contract with R. Cunningham (FC)
Cunningham CA Lawrence Livermore officials.
J. Malaro (RES)
F. Gillespie (RES) 10/9/85 Willste Meeting to discuss remedial action Reps of B&W Loysen Room 517 efforts on the upper slope burial P. Loysen (FC) site at Babcock & Wilcox Parks J. Roth (RI)
Township site.
10/19-11/1/85
- Vienna, Serve as U.S. expert or observer on J. Cook (FC)
Cook Austria a Technical Committee on the Assessment of the Radiological Impact from the Transport of Radioactive Materials (IAEA).
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NMSS MEETING NOTICES DlVISION OF WASTE MANAGEMENT g
I DOCKET ATTENDEES /
DATE/ TIME NUfBER LOCATION PURPOSE APPLICATION NRC CONTACT 10/8-10/10 Bethesda, MD Annual Agreement State DMattson DMattson Meeting - LLW disposal i
10/7-11 Tulsa, OK Nat'l Congress of CRussell American Indians States / Indian tribes CRussell l
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RES MEETING NOTICES September 27, 1935 m
- DOCKET ATTENDEES /
DATE/ TIME Nutt3ER LOCATION PUPPOSE APPLICANT NRC CONTACT I
9/30-Vienna, Austria IAEA TRC Operations mtg Norberg Norberg 10/4 10/6-9/85 Alexandria, VA 1985 Annual fleeting of the Society Abramon Abranison for Risk Analysis 10/3/85 Dept. of Interagency Coex ittee on Minogue/
Tomlin 9:30 AM Consnerce Standards Policy Tomlin 1
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' e i
RII MEETING NOTICE w
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i DOCKET
' ATTENDEES /
l DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT 10/01/85 Surry, VA Full-scale Emergency Licensee and Selected Stohr Exercise RII Staff Members l
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REGION 111 MEETING NOTICES i
i GEEK ENDING:
September 27, 1985 DOCKET ATTENDEES /
DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT
]
s 10/15/85 50-456 Glen Ellyn, IL BCAP
. Commonwealth Edison 10 a.m.
50-457 Braidwood J.G. Keppler & staff J.G. Keppler e
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