ML20136J069
| ML20136J069 | |
| Person / Time | |
|---|---|
| Issue date: | 11/20/1985 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-851115, NUDOCS 8511250272 | |
| Download: ML20136J069 (42) | |
Text
-
e' hhk)[_-
4
,.i November 20, 1985 For: The Commissioners From: T. A. Rehm, Assistant for Operations, Office of the EDO
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING NOVEMBER 15, 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 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* '
s Regional Offices L CRGR Monthly Report M Executive Director for Operations N*
Items Addressed by the Commission 0 Meeting Notices P Proprietary or Other Sensitive Information (Not for Q external distribution)
- No input this week. ~
/
_/
T. A. R s for Operations Office of the Executive Director for Operations
Contact:
T. A. Rehm, ED0 492-7781 0511250272 851120 PDR COMPE NRCC WEEKLYINFOREPT PDR
l' <
f' HI$HLIGHTSOFWEEKLYINFORMATIONREPORT
- WEEK ENDING NOVEMBER .15,1985 Seabrook At 7:20 a.m. on November 7, 1985, the plant operators synchronized the power plant's turbine generator with the New England Power Grid System and tested the plant power generating systems at output levels up to 80 megawatts of power i for about 9 minutes.
! Grand Gulf, Unit 1 l On November 6,1985, a TDI' emergency diesel generator was shutdown during a surveillance test because 4of overspeed. The plant has been in a planned outage since October 12 and is scheduled to restart November 22. The diesel engine is being disassembled to ascess the damage that resulted from the overspeed and consequent vibrations of the engine.
- N Limerick ,
i The Philadelphf a Electric Company, on November 5,1985, petitioned the Commission to review an issue arising from ALAB-819, dated October 22, 1985, on the Limerick Generating Station. The staff must file its reply, provided the staff opposes the petition, by November 20, 1985.
Watts Bar Unit 2 {
l On November 13, 1985 TVA provided NRC with two announcements. One described a reassessment program for construction of Unit 2 at Watts Bar. In addition, a reduction in the trades and labor (T&L) workforce from 1550 to 850 for the next 2 to 3 months and in the annual salary workforce from 739 to 550 was announced. The T&L workforce may be increc:cd te abcut 1000 at a later time. TVA also announced they were a
releasfog copies of the INPO final report.
a The othsr announcement was of the following reassignments of construction managers at Watts Bar: Floyd Smith replaces H. J. Fischer as Construction Engineer; Ben F. Painter replaces C. H. Jetton as General Construction Superintendent; and Bobby J. Thomas replaces Shelton Johnston as Quality Manager. Fischer goes to the construction
<uppo'rt group at Sequoyah; Jetton takes responsibility for field construction of the Watts Bar training center; and Johnston moves to Bellefonte in a Quality Manager type position.
,a NFS-Erwin Strike by OCAW members continues. There has been some negotiating between the Union and NFS within the last five weeks but no' resolution has been reached.
NFS is conducting limited operations of the HEU production, scrap recovery and R&D facilities. No problems with site operations have arisen to date.
. Davis-Besse The plant remains in cold shutdown. The circulating water canal is drained.
n Decay heat loop No. 2 is drained and out of service for maintenance.
NOV 151985 ,
OFFICE OF ADMINISTRATION Week Ending November 15, 1985 ADMINISTRATION OF THE FREEDOM 0F INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Carryovers, 1984 179 23 Received, 1985 755 41 Granted 594 30 Denied 171 16 Pending 169 18 ACTIONS THIS WEEK Received Donald Dilks, Requests copies of the winning proposal and the contract DDD Company awarded to Computer Data Systems, Incorporated, for (85-741) maintaining mailing lists, publications inventory, fulfilling distribution requirements and generating mail labels.
Barbara A. Hannett, Requests a copy of Westinghouse Drawing No. 360F05EQ01.
Transnuclear, Inc.
(85-742)
Ellen M. Neering, Requests copies of all records in the possession of the Barris, Sott, ACRS related to compensation for work performed by Denn & Driker Dr. Jorj Osterberg for ACRS and records indicating the (85-743) amount of time spent by Dr. Osterberg working for ACRS.
Mary Jo Little Requests information concerning the accident at TMI.
(85-744)
Steven Aftergood, Requests copies of all papers delivered at the Committee to International Meeting on Reduced Enrichment for Research Bridge the Gap and Test Reactors held October 14-16, 1985, in Petten, (85-745) Netherlands.
William R. Pearce Requests a copy of the transcript of the ACRS Grand Gulf (85-746) Subcommittee Meeting on January 18, 1974, referenced on page 196 of ACRST-062.
Roger A. Keller, Requests copies of F0IA request F01A-85-682 and NRC's Mallinckrojt, Inc. response.
(85-747)
CONTACT: J. M. Felton ENCLOSURE A 492-7211 NOV -151985
2
. Received. Cont'd Charles Barnes Requests copies of all Docket 40-2061 facility docket (85-748) file records dated from January 1,1968, through December 31, 1973, that were not previously placed in the PDR.
Kenneth T. White Requests a list with five categories of infomation (85-749) regarding manufacturers who install sealed sources requiring leak testing into devices with registered designs for distribution to licensees.
' -Kenneth T. White Requests a list of sources with registered designs that (85-750) require leak testing, the leak testing interval, and a list of manufacturers who have made these sealed sources, and the types and numbers assembled.
(HRCemployee) Requests a list of names and addresses of persons (85-751) contacted during his 1981 security clearance.
Charles Barnes Requests records that would identify docket 40 files (85-752) placed in retirement before the computer system to track files retirement became operable in 1974.
1 Jessie L. Burke Requests a list of the laboratories, with their (85-753) addresses, in the US that have equipment to test for the
!- presence of plutonium in a living body and references to articles, book, or texts which deal with the testing for plutonium in the body after death.
S.E. Thoms Requests copies of all health physics procedures and other procedures related to the testing, calibration,
- 1 (85-754) etc., of portable radiation detection instrumentation
' for the University of Michigan's nuclear reactor.
3 i) Requests copies of all AEC records related to 4- Charles Barnes i (85-755) transportation incidents III-69-03 of March 5,1969, and III-70-04 of May 16,1970, related to United Nuclear i
i Corporation and Kerr-McGee's Cimarron Facility.
Granted Patty Day, In response to a request for a copy of SECy-85-150, and NUS Corporation any applicable supplements, made available a' copy of (85-689) SECV-85-150. Informed the requester that there are no supplements to SECY-85-150.
L Diane Curran, Ir response to a request for a copy of a June 27, 1985, Harmon & Weiss m iorcndum for William J. Dircks from Harold R. Denton, (85-693)
Subject:
Commission Paper on Station Blackout, made j
available a copy of the requested record.
I Billie P. Garde, In response to a request for all records related to NRC's Government Inspection Report 50-456/80-04,50-457/80-04 issued Accountability June 10, 1980, regarding the Braidwood nuclear power Project plant,'infomed the requester that 16 records subject to this request are already available at the PDR.
NOV 15198,.
3 '(85-697) ENCLOSURE A
3 Granted, Cont'd Lyle Graber, In response to a request for a copy of NRC's Office of NUS Corporation Inspector and Auditor's report entitled " Review of the (85-715) Committee to Review Generic Requirements," made available a copy of the requested report.
Shlomo P. Neuman, in response to a request for a copy of the nonproprietary The University of version of the technical proposal in response to Request Arizona for Proposal number RS-RES-85-ll4 entitled " Flow of (85-720) Groundwater and Transport of Contaminants through Saturated Fractured Geologic Media from High-Level Radioactive Waste," made available a copy of the requested record.
Gary Redmore, In response to a request for a listing of NRC's byproduct Syncor material licensees in Region I, made available the International requested list.
Corporation (85-722)
Denied None N LOSURE A NOV 151985
WEEKLY INFORMATION REPORT DIVISION OF CONTRACTS WEEK ENDING NOVEMBER 15, 1985 RFP ISSUED RFP No.: RS-NMS-86-001 title: " Technical Assistance in Environmental and Socioeconomic Assessments"
Description:
Contractor shall provide technical assistance to NRC in the review of DOE programs and site characterization plans relating to the development of Environmental Impact Statements.
Period of Performance: Three years Sponsor: Office of Nuclear Material Safety and Safeguards Status: RFP issued on November 12, 1985. Proposals due December 12, 1985.
RFP No.: RS-ADM-86-250
Title:
Course "NRC: What It Is and What It Does"
-Description: Presentation and development of material for the above course to be presented approximately four times per year in Bethesda, Md.
Period of Performance: Two years Sponsor: Office of Administration Status: RFP issued on November 14, 1985. Proposals due December 17, 1985.
PROPOSAL UNDER EVALUATION RFP No.: RS-SEC-86-201
Title:
" Stenographic Reporting Services"
Description:
Contractor will provide stenographic reporting services for NRC Commission Meetings held in the Washington, D.C.
Metropolitan Area.
Period of Performance: Two years with an option to extend one additional year.
Sponsor: Office of the Secretary Status: The competitive range has been established and negotiations are scheduled for November 15-19, 1985.
ENCLOSURE A NOV 151935 L
OFFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending November 15, 1985 Seabrook l At 7:20 a.m. on November 7, 1985, the plant operators synchronized the power plant's turbine generator with the New England Power Grid System and tested the plant power generating systems at outpat levels up to 80 megawatts of power for about 9 minutes. Steam required was generated from heat produced by running the reactor coolant pumps.
Grand Gulf, Unit 1
-On November 6, 1985, a TDI emergency diesel generator was shutdown during a surveillance test because of overspeed. The plant has been in
-a planned outage since October 12 and is scheduled to restart November
- 22. Prior to the diesel generator test, the oil in the governor had been drained for maintenance on the governor. The governor was refilled with oil prior to the engine start but after the shutdown, no
- oil was visible in the governor gage glass.
! The diesel engine is being disassembled to assess the damage that resulted from the overspeed and consequent vibrations of the engine.
Presently, two rod assemblies, one main bearing and four pistons have been removed. A connecting rod bearing link pin bushing and main bearing nave been found to be damaged.
Licensee plans to continue to disassemble the. engine to assess damage and replace damaged componeRs. Licensee has briefed the Resident Inspector, NRR and Region II by telephone and will continue to advise
- the Projec.t Manager and the TDI Project Group of results-of its inspection and plans for reassembly. The TDI Project Group is planning a visit to the plant to see the damaged parts after disassembly is completed'early next week.
Kewaunee Plant - Trip Breaker Failures IE Bulletin 85-09 requires plants without the shunt trip to test all breakers within seven days. The Kewaunee plant tested the two bypass breakers, two main breakers and a spare breaker. One bypass breaker failed the 20-ounce test. One main breaker failed the'20-ounce test and was replaced with a spare that passed the test. At this time (1600 EST November 7, 1985) the plant is at full power with two operable main breakers and an operable bypass breaker. By coincidence Region III had a member of the " Cook breaker response team" on-site throughout this event. The test program was started at 1010 EST November 7, 1985. The licensee has retested one of the failed breakers and it passed seven successive 20-ounce tests. The remaining failed breaker is being ENCLOSURE B
- refurbished for further testing. The licensee is trying to determine the root cause of failure, so far without success.
l NOV 151985
Limerick The Philadelphia Electric Company, on November 5, 1985, petitioned the Commission to review an issue arising from ALAB-819, dated October 22, 1985, on the Limerick Generating Station. The licensee contends that the Appeal Board has created "a wholly new requirement for backup medical support...for onsite plant workers who might be contaminated and injured in a plant accident." The issue concerns whether the Hospital of the University of Pennsylvania, located about a 45 minute drive from the Limerick site, is too distant to serve as an adequate backup hospital.
The staff must file its reply, provided the staff opposes the petition, by November 20, 1985.
, Watts Bar Unit 2 i
On November 13, 1985 TVA provided NRC with two announcements. One described a reassessment program for construction of Unit 2 at Watts Bar. In addition, a reduction in the trades and labor (T&L) workforce from 1550 to 850 for the next 2 to 3 months and in the annual salary workforce from 739 to 550 was announced. The T&L workforce may be increased to about 1000 at a later time. TVA also announced they were releasing copies of the INP0 final report.
j The other announcement was of the following reassignments of construction managers at Watts Bar: Floyd Smith replaces H. J. Fischer as Construction Engineer; Ben F. Painter replaces C. H. Jetton as General Construction Superintendent; and Bobby J. Thomas replaces
- Shelton Johnston as Quality Manager. Fischer goes to the construction support group at Sequoyah; Jetton takes responsibility for field construction of the Watts Bar training center; and Johnston moves to Bellefonte in a Quality Manager type position.
I n
i ENCLOSURE B NOV 151965 5 '
NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT WEEK ENDING NOVEMBER 15, 1985
- 1. DEFUELING Following the successful integrated testing of the defueling canister transfer systems in the. Reactor Building and the Fuel Building, two fuel canisters were loaded into the sleeves of the Canister Positioning System (CPS). The debris bed in the region of the CPS has been excavated such that the CPS is free to rotate with the canister bottoms at the 308'6" elevation. The Defueling Water Cleanup System (DWCS) is functioning with its four filter canisters installed in the deep end of the fuel transfer canal. On November 12, 1985, General Public Utilities Nuclear (GPUN)
Corporation received permission from the NRC onsite staff to load the fuel canisters with fuel debris. Using the vise grip tool, the defueling workers placed into a fuel canister the first piece of debris, a broken piece of fuel rod. On November 14, 1985, defueling workers picked and placed the first piece of endfitting into the fuel canister.
Difficulties were encounted with endfittings which are fused together.
Fused endfittings have to be separated in order to fit into the fuel canisters. The licensee is evaluating methods to separate these fused endfittings.
typical defueling team consists of a radiation control technician, two tool operators, an equipment controls panel operator, a camera operator, and an NRC licensed fuel handling senior reactor operator who is in continuous direct communication with the rest of the team. NRC staff observations indicate that licensee performance to date has been excellent. Defueling operators have demonstrated a thorough knowledge of procedures and safety precautions.
- 2. PLANT STATUS
- The facility remains in long term cold shutdown with the Reactor Coolant System (RCS) vented to the reactor building atmosphere and the reactor vessel head and plenum assembly removed from the reactor vessel.
ENCLOSURE B NOV 151985
2
- 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 ,
t shallow ends ~of the fuel transfer canal. The deep end is filled with water to a depth of about 20 feet (about 5 feet above the top
- of the plenum).
- The modified internals indexing fixture is installed on the reactor
. vessel flange and is flooded to elevation 327 fcet 5 inches (151 feet above the top of the core region). The defueling platform is installed over the Internal Indexing Fixture 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 71*F to 95'F 2 'with an average of 83 F.
- The average reactor building temperature is 60 F. The reactor building airborne activity at the Westinghouse platform is 1.2 E-7 uCi/cc Tritium and 8.9 E-10 uCi/cc particulate, predominantly Cesium 137.
Spent Fuel Pool "A" is flooded to a depth of 20 feet. About 6 feet of water is over fuel canister-storage racks.
- 3. WASTE MANAGEMENT l
- One train of the reactor vessel filtration portions of DWCS was started on November 13, 1985. The system operated for about 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> before being shutdown when filter differential pressure 4 reached the procedural limit. It is believed that the filters
~
plugged micron)particles quickly when initially1oaded with theinvery in suspension fine (less the RCS. than It was 0.5 then operated Ntermittently at reduced flow rates until November 15, 1985. The short period of operation substantially improved the RCS -
water clarity. The DWCS filter effluent turbidity remained at 0.1
- to 0.2 NTU's. On November 15, 1985, the second train was placed in .
operation.- .
1
- Processing of batch 126 continues, Fuel Transfer Canal recycle
! through both Trains and."B" cation sand filter. A total of 181,155 gallons has been, processed in batch 126 tordate.
4 EPICOR II is temporarily shutdown while changing out liners.
- Total volume processed through SDS to date is 3,373,117 gallons, and the total volume processed through EPICOR II is 2,700,737 gallons.
- 4. DOSE REDUCTION / DECONTAMINATION ACTIVITIES
- Decontamination activities are continuing on the 281' level of the auxiliary building. Scabbling of reactor coolant bleed tank cubicles is in progress.
- 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.
- Decontamination of the pressurizer and "A" D-ring is in progress.
ENCLOSURE B l
NOV 151985
3
- 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 October 27 through November 2, 1985. A gamma scan detected no reactor related activity.
- The Lancaster water sample taken at the water works intake and analyzed by EPA consisted of a seven day composited sample taken from October 27 through November 2, 1985. A gamma scan detected no reactor related radioactivity.
4
- The NRC catdoor airborne particulate sampler at the TMI Site collectad a sample between November 7 and November 13, 1985. No
- reactor related radioactivity was detected. Analysis showed Iodine-131 and Cesium-137 concentrations to be less than the lower limits of detectability.
- 6. REACTOR BUILDING ACTIVITIES
- The initial phase of defueling the reactor core is in progress.
- Installation of the vacuum defueling system is in progress.
- 7. AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES Installation of the balance DWCS continued.
- Spent Fuel Pool has been flooded to a depth of about 20 feet (about 6 feet above the top of the fuel canister storage racks).
- 8. NRC EVALUATIONS IN PROGRESS c .
- Technical Specification Change Request number 49.
- Recovery Operations Plan Change number 31.
- SDS Technical Evaluation and ' System Description Update.
- - Core Stratification Sample Safety Evaluation.
- Defueling Water Cleanup System Technical Evaluation Report, Revision 7.
- Containment Air Control Envelope Technical Evaluation Report, Revision 5.
- Solid Waste Facility Technical Evaluation Report.
9*. PUBLIC MEETING The next meeting of the Advisory Panel is scheduled for 11:00 AM, November 19, 1985, in Washington, DC, before the NRC Commissioners. The next meeting in the TMI area is scheduled for December 12, 1985, at the i
Harrisburg, PA Holiday Inn, 23 South Second Street, Harrisburg, PA, from 7:00 PM to approximately 10:00 PM.
ENCLOSURE B NOV 151985
4 Persons desiring the opportunity to speak before the Panel are asked to contact Mr. Thomas Smithgall at 717-291-1042 or write to him at 2122 Marietta Avenue, Lancaster, Pennsylvania 17603.
I e
I i
f l
ENCLOSURE B NOV 151985
OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS
- .. Items of Interest Week Endina November 11, 1985 Near-Term NRC Actions Under the Nuclear Waste Policy Act (NWPA)
+
Section: 137 of NWPA: Transportation of HLW Action: On November 19-21, 1985 DOE's Office of Civilian Radioactive Waste Management (OCRWM) will sponsor a workshop in Atlanta to discuss planning for transportation under provisions of the NWPA, and to receive comments on the draft Transportation
+
Institutional Plan.
J Status: Three members of the NRC Division of Waste Management Staff
' are scheduled to attend this workshop.
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
> Radioactive Waste will become effc ctive November 18, 1985 (50 FR 4003).
Status: Staff is reviewing NRC's high-level waste criteria for conformance with EPA standards and will provide a proposed rule to the EDO and the Commission in January,1986.
Section: 141 of NWPA: Licensing of MRS ,
Action: .
NRC is currently developing revisions to 10 CFR Part 72 to provide the licensing framework for the MRS, should it be authorized by Congress. If authorized, NRC will review DOE's license application and make. the necessary licensing determinations.
Status: CRGR had been scheduled to be briefed concerning the proposed revisions on November 13, 1985, but the meeting was cancelled, and will possibly be rescheduled for the end of November, i
Also, DOE has submitted the Environmental Assessment of the l MRS to the State of Tennessee as of November 8,1985.
l l Section: 112(b) of NWPA: Site Nomination and Reconnendation Action: DOE announced on October 30, 1985, that the date for site nomination and recommendation with the accompanying EAs cited in the draft PDS as November,1985 has been extended by 60 days to accommodate for the NAS ranking methodology review. Nomination, recommendation, and final EAs are now l expected by late February, 1986. ENCLOSURE C Status: As of November 12, 1985, DOE will issue the SCPs for basalt and tuff sites, as scheduled in the draft POS, in March 1986, NOV 151965 one month after site nomination and recommendation.
--ywyy,y -y-w--g-wv-w+---ww g,- r- + - --,---.-y- --r*
. _ =- . -- .- ._ - - - . _ _ - _ _
n
- . i NFS-Erwin Strike by OCAW members continues. There has been some negotiating between the Union and NFS within the last five weeks but no resolution has been reached.
4 NFS is conducting limited operations of the HEU production, scrap recovery and R&D facilities. No problems with site operations have arisen to date.
- Monitored Retrievable Storage (MRS)
On November 13, staff members of NMSS:FC, ELD and CA met with Ms. Dana Isherwood from the staff of Senator Gore (Tennessee) at her request to discuss topics related to the MRS proposal being developed by D0E.
NRC staff explained the role of NRC and the interaction with DOE on the MRS proposal, noting that the Comission has a neutral position on the need for MRS. In response to questions, the staff indicated that recomendations of the Oak Ridge-Roane County MRS Report were matters for DOE consideration, and that any agreements between DOE and local agencies on MRS,should it be authorized by Congress, would be con-sidered by the NRC only from its regulatory jurisdictional role and relation to safe operations. The NRC role in transportation was discussed, including response to general questions on NRC transportation
- safeguards requirements. The status of proposed changes to 10 CFR l Part 72 to accommodate MRS licensing was given and the meeting concluded with discussion of reactor spent fuel storage capabil1 ties, including the status of rod consolidation and dry storage methocologies.
IAEA Technical Comittee
, During the week of October 21-25, 1985, Mr. John R. Cook, NMSS, participated as
, U.S. expert in an IAEA Technical Comittee meeting on the " Assessment of the Radiological Igact from the Transport of Radioactive Material." The purpose of the meeting was to prepare a sumary statement on the radiological igact of transporting radioactive material worldwide based on data available from member states relating to both normal conditions of transport and to accidents and incidents. In addition, the Comittee was to identify those transportation l areas where future Agency efforts and resources should be directed. Most of l the discussion on transportation igacts focused on the members' experiences in e
l using INTERTRAN, a computer code developed by Sweden in cooperation with the l- U.S. (it is a de~rivative' 9f the U.S. developed RADTRAN code) to assess the
. radiological igacts of transportation. The consensus view was: the incident l .
free and accident sections of INTERTRAN should be considered separately; i although a number of deficiencies exist in the incident free section. This
! section hss proved useful and should be supported, and the accident section suffers from a number of important deficiencies but is useful to exchange infonnation between countries.
With respect to available data on exposures from routine transport of radioactive material, it was concluded that exposures are low, and that it could be inferred
, that the transportation of non-fuel-cycle materials contributes significantly more to these exposures than does the transportation of fuel-cycle materials. In particular, the transportation of molybdenum / technetium generators for medical uses was found to be the largest single contributor to routine transportation l impacts in the United Kingdom, France, and Italy.
ENCLOSURE C
! NOV 151935 l_ - - _ _ _ _ _ _ . _ , - _ . - - . , , -
With respect to impacts from accidents, very few members were in a position to present information. It was noted that a number of the transportation incidents that have occurred (e.g., leaking packages upon delivery to destination) are related to quality assurance failures. There simply have not been enough serious transportation accidents involving radioactive materials to prepare a summary statement on measured exposures and impacts.
For future efforts, the Comittee recomended the wort continue to improve transportation igact assessment models; however, earlier suggestions of conducting global transportation igact assessments using these models may have been overly ambitious. Many members reported that large increases in waste shipments were anticipated in the future, perhaps egloying dedicated transportation systems. The Comittee recommended that the effect of significant changes in shipment patterns be assessed with respect to current codes and practices. Finally, the Comittee recomended that the shipment of medical generators be examined to assure that exposures have been ' optimized'.
All recomendations from the Technical Comittee will be forwarded to the IAEA Standing Advisory Group for the Safe Transport of Radioactive Material (SAGSTRAM) for consideration at their next meeting, currently scheduled for March 1986.
IAEA Scientific Programme Comittee for PATRAM '86 During October 28-31, 1985, Mr. John R. Cook, NMSS, participated as U.S.
representative in an IAEA Scientific Programe Comittee meeting for the symposium on " Packaging and Transportation of Radioactive Materials" (PATRAM 1986) to be held in Davos, Switzerland in June 1986. The purpose of the meeting was to select papers, structure sessions, and recomend session chairmen for the symposium.
The U.S. has one of three plenary session addresses; and DOE, a funding sponsor of the symposium, is expected to provide a senior official from the Waste Program area (perhaps Mr. Rusche) to give this talk.
In all, the IAEA secretariat received 252 technical papers for consideration for 145 oral and poster session slots. The most common topical areas among the j-papers were package design and testing; emergency response, quality assurance, and training were among the least common topi':s. As the U.S. had submitted a total of 112 papers, more than 4 times that of any other member, the U.S. was i expected to eliminate the largest number of submittals. The final paper rejection rate for the U.S. was about 25 percent of submittals, the same as for the United Kingdom. France and. Germany had about 15 percent, with smaller percentages for other members. All four technical papers submitted by NRC
! staff were accepted by the Comittee.
ENCLOSURE C NOV 151985
Meeting with Ms. Lively and Staff Concerning Collection of Data on the Generation, Treatment, and Disposal of Radioactive Wastes from Institutions, Radiopharmaceutical Manufacturers and Biomedical Research Laboratories Mr. Richard E. Cunningham, Director of FCMS, and a member of his staff, Dr. L. A. Roche, will meet on Friday, November 22,1985, with Ms. Carol A. Lively, Executive Director of the American College of Nuclear Physicians (ACNP), and her staff to discuss the data that the ACNP is collecting (under DOE contract) regarding the generation, treatment and disposal of institutional waste, as well as, waste generated in the manufacture of radiopharmaceuticals and in biomedical research and treatment. These data may be useful to the NRC in its endeavor to review and change, if appropriate, its regulations.
GA Technologies, Inc.
On November 7,1985, Dr. Keith E. Asmussen (Manager, Licensing Administration) 1 and Mr. Alexander L. Galli (Manager, Security), GA Technologies, Inc. (GA) met with members of the staff to discuss the reorganization at GA. Dr.' Asmussen will incorporate the Commission comments in revised pages to their SNM-696 license and submit them as a request to amend the license in accordance with the change in organization.
4 i
ENCLOSt'RE C i
NOV 151985
OFFICE OF INSPECTION AND ENFORCEMENT Items of Interest Week Ending November 15, 1985
- 1. The following Significant Enforcement Actions were taken during the past week:
- a. EN 85-63A, Imposition of Civil Penalty in the amount of $3,750 was issued November 14, 1985 to Metro Health Center (Erie, PA). This action was based on multiple violations that represent a breakdown in management oversight and control of the radiation safety program.
The licensee responded to the Notice of Violation and Proposed Imposition of Civil Penalty (EN 85-63 dtd. September 11, 1985) in a letter dated October 20, 1985. After careful consideration of the
- licensee's response, the staff has concluded that the violations die occur as set forth in the Notice.
- 2. The following IE Preliminary Notifications were issued during the past week:
- a. PNO-I-85-86, Nuclear Pharmacy, Inc. (Philadelphia, PA), Strike By Nuclear Pharmacy, Inc. Delivery Drivers.
PNO-II-85-105A, Florida Power and Light Company (St. Lucie Unit 1),
b.
Upper Guide Structure Lifting Rig Failure (Update).
- c. PNO-II-85-108, Mississippi Power and Light Company (Grand Gulf Unit 1), Inspection of Diesel Generator For Damage,
- d. PNO-III-85-93C, American Electric Power (D.C. Cook), Failure of Reactor Trip Breaker (Third Update).
- e. PNO-V-85-76, Arizona Nuclear Power Project (Palo Verde Units 1, 2, &
3), Extended Plant Shutdown While Assessing Adequacy of Reactor Coolant System Line Stop Fasteners. 3
- f. PN0-V-85-77, Washington Public Power Supply System (WNP-2), Trip of WNP-2.
the past week:
None, i
I i ENCLOSURE D NOV 151985 1
l L- - _ _ _ _
- 4. Other Items i
- a. International Symposium Deputy Director, Division of Emergency Preparedness and Engineering Response presented a paper entitled " Emergency Preparedness for Nuclear Power Facilities in the USA" at the International Symposium on Emergency Planning and Preparedness for Nuclear Facilities in Rome, Italy on November 4-8, 1985.
- b. Construction Appraisal Team Inspection The Construction Appraisal Team returned to the South Texas plant this week to complete its inspection. The exit meeting with the licensee is scheduled.for November 22, 1985.
- c. Vendor Program The Vendor Program Branch, Division of Quality Assurance, Vendor, and Technical Training Programs conducted the following inspections -
this week:
(1) ' Westinghouse, Columbia, SC - to review the QA program and its implementation; review conditions related to specification, manufacturing, and QA practices which may affect feel quality.
(2) Westinghouse, Pittsburgh, PA - to review records, QA program implementation for breaker refurbishment activites, and witness tests on the failed D.C. Cook reactor trip breakers.
- d. Incident Response (1) On November 12, 1985, the Chief, Incident Response Branch, Division of Emergency Preparedness and Engineering Response, (DEPER), conducted a tour of the NRC Operations Center for the Director, Emergency Planning Office, Mr. Kim, and the Scientific Attache, Mr. Hong, Republic of Korea. This tour discussed the agency's incident response program.
(2) The Incident Response Branch, DEPER, is coordinating the NRC participation in REX-86 ALPHA exercise which is being conducted by FEMA in cooperation with the D00. This is a joint civil /
military mobilization exercise which began on November 12 and will run through November 22, 1985.
ENCLOSURE D NOV 151985
- e. Emergency Response Training On November 11, 1985 an emergency response training session was held for Commissioner Assistants in the NRC Operations Center.
- f. Augmented Response Activities Representatives of Engineering and Generic Comunications Branch, Division of Emergency Preparedness and Engineering Response, and Region II visited the Shearon Harris Energy & Environment Center, Raleigh, NC on November 13, 1985 and the Brunswick site on November 14, 1985. This was for the augmented followup of MSIV failures at the Brunswick plant on September 27, 1985.
- g. Quality Assurance (1) A representative of the Quality Assurance Branch (QAB), Division of Quality Assurance, Vendor, and Technical Training Programs participated in a public meeting on November 5-6, 1985 in Granbury, TX concerning status of Comanche Peak Response Team Program Plan activities.
(2) A representative of QAB visited Sargent and Lundy offices in Chicago, IL on November 5, 1985 in conjunction with inspection activities associated with implementation of corrective actions resulting from Byron 1 IDR and IDVP, and Clinton IDVP.
(3) A representative of QAB participated in a meeting of the AS'iE Boiler and Pressure Vessel Code's subgroup on general reapire-ments in New York City on November 13, 1985.
- h. . Civil Penalties Paid On November 12, 1985, payment in th'e amount of $50,000 was received from Baltimore Gas and Electric (Calvert Cliffs) for enforcement action (EA 85-102) relating to the failure to maintain the operability of the installed PASS.
- 1. Conference Representative of Safeguards Materials Program Branch, Division of Inspection Programs attended the " Conference on Recent Advances in Hazardous Materials Research: An International Exchange," in Lake Buena Vista, FL this week.
- j. Inspection Program Assessment Representative of Safeguards Materials Program Branch, Division of Inspection Programs is in Kansas City, M0 this week on an assessment of inspection programs with representatives of Region III.
ENCLOSURE D NOV 151985
.. --. -- - .-_ - . .. - - .- = - .
a 0FFICE OF NUCLEAR REGULATORY RESEARCH Items of Interest Week Ending November 15, 1985 FLECHT-SEASET l
The final report for the Full-Length Emergency Core Heat Transfer-System l Effects Tests and Separate Effects Tests (FLECHT-SEASET) program has been accepted for publication. The FLECHT-SEASET program is a cooperative program i
l conducted over the past eight years by(the Westinghouse Electric Corpora
. the Electric Pcwer Research Institute i
Comission. The objective of the program was to obtain data and perform i analysis that would improve the understanding of the complex two-phase flow phenomena that occur during a postulated'oressurized water reactor (PWR) l loss-of-coolant accident (LOCA). The "FLECHT SEASET Program Final Report,"
which will be published as NUREG/CR-4167, summarizes the highlights and major j findings of the program. The report indicates areas in which the results of
-the program can contribute to revising the current licensing requirements for
!- LOCA safety analysis. It also identifies several technical areas in which the FLECHT-SEASET data and analysis can lead to improved safety analysis modeling.
The report summarizes the results from the natural circulation test series, which investigated the single-phase, two-phase, and reflux condensation cooling The tests and modes of a scaled PWR under small-break LOCA conditions.
subsequent analysis constitute one of the few complete sets of data for these j
cooling modes in which full-height, multi-tube steam generators with sufficient instrumentation were used to examine primary-to-secondary heat transfer in the gener a tors. Contract closeout will commence after the publication of the final report.
BWR FIST Program The final reports for the Boiling Water Reactor (BWR) Full Integral Simulation This Test (FIST)programhavejustbeencompleted(NUREG/CR-4127and4128).
i marks the completion of over a decade of cooperative research involving BWRs This sponsored by the NRC, EPRI, and the General Electric Company (GE).
' research started in the mid 1970's.with the Two-Loop Test Apparatus program and i
continued with the Sector Steam Test Facility program which investigated emergency core cooling system performance during large-break LOCA in BWRs.
1 Later testing in the FIST facility improved the simulation of large LOCA and extended the simulations to include small and intermediate LOCA and non-LOC transients. These experimental programs have been closely linked to the code development efforts and results of these Thetests resultsused to evaluate of these programs the have calculation also capabilities of TRAC-BWR and=RAMONA.
L been used by GE to develop an improved licensing evaluation model.
An agreement, has also been reached among the sponsors to not dismantle the
- FIST facility for at least a year.
i ENCLOSURE E I NOV 151985
.- < - va w m n -,,,----n.mmvmgw-,m> -,e nnw~.-.,--me-,w.,,.e,ww-.-.,,-------,.----,.>,-rm---,.-,~.--v-
n .- .
20/3D Program The German Upper Plenum Test Facility (UPTF) located in Mannheim, Federal Republic of Germany, which provides full-scale data on large-break loss-of-coolant accidents, is undergoing a series of commissioning tests which are now projected to continue about 6 months longer than the earlier i estimation (June 1985). The main tests are scheduled to start in May 1986. Kraftwerk Union (KWU), which constructed the UPTF, is operating on a three shift-work schedule to meet the May 1986 milestone. RES and the Japan Atomic Energy Research Institute (JAERI) emphasized the importance of minimizing any further delay. The main cause for the delay was that the facility had to be modified in order to avoid a potential water hamer problem .
Public Meetings on Protection of Workers in Uranium Processing Facilities j The Office of Nuclear Regulatory Research will conduct two consecutive public meetings on two topics relating to the protection of workers in uranium processing facilities. The meetings, which are open to the public, will be held from 8:30 a.m. to 5:00 p.m. on December 3 and 4, 1985, in the auditorium of the General Services Administratinn Building, 18th and F Streets, N.W.,
Washington, D.C. The first meeting will review the state-of-the-art of physical and chemical techniques for the measurement of very low leyels of l
uranium in biological specimens. Such techniques of high sensitivity are needed because present detection levels are not sensitive enough to always indicate when action is necessary. The second meeting will focus on recent biological research related to the validity of the current toxic limit for uranium. Recent animal experiments suggest that this value should be lowered. The NRC has invited scientists that have had extensive experience on these subjects to speak at these meetings. The meetings will also provide interested persons an opportunity to make statements on or ask questions about l these topics. * ~
l R. B. Neel i
i Recently Issued Publication R. G.1.152, " Criteria for Programable Digital Computer System Software in Safety-Related Systems of Nuclear Power Plants" l
l
. L.
l l
ENCLOSURE E NOV 151985
. . . ~ . ,~ _ - _ .. . _ . _.
l l
3 RES Rulemaking Activities i Emergency Core Cooling Systems; Revisions to Acceptance Criteria
- (Part 50) (Appendix K?
a
. The proposed rule would amend regulations concerning acceptance criteria for emergency core cooling systems (ECCS) by changing the methods used to t ' demonstrate that an ECCS would protect the nuclear reactcr core during a loss-of-coolant accident. Because the proposed rule represents a significant change in a regulatory requirement, the staff is currently preparing a sumary of ECCS research performed over the last 10 years which will serve as the i technical . basis for the proposed rule and a regulatory guide which will provide definition of what constitutes an acceptable best estimate model and acceptable methods of performing the uncertainty evaluation.
4 A meeting was held between NRR and RES staff on November 8,1985, to resolve technical differences concerning the rule and the associated regulatory guide.
It was agreed that the 95 percent certainty limit would not be specifically l
- mentioned in the rule. Rather, the rule would refer to "a high degree of certainty." The accompanying discussion would elaborate on this and mention
, the 95 percent certainty limit. The regulatory guide would then describe an acceptable method for achieving this degree of certainty. NRR would be provided with technical documents that describe in detail specific codes,
' models or methods referenced in the regulatory guide, so that they may perform an evaluation regarding acceptability. ,
i Consideration of Earthquakes in the Context of Emergency Preparedness (Part 50)
The final rulemaking package was signed by the EDO on August 20, 1985. A l Comission meeting was held on September 9,1985.- The Commission is expected to give the staf' further instruction. An ACRS meeting was held on October 9, 1985. This meeting was held at the Comission's request in order to discuss SECY-85-283. ACRS input for this rulemaking was provided to the Comission on October 17, 1985. In accordance with Comissioner Asselstine's request, OGC has developed a position on reproposing the rule due to new arguments being presented in the current paper. This is beir.g discusseo between OGC and ELD l
to identify any differences with this position. On Novem)er 7, 1985, the ACRS discussed their coments on this issue with the Comissior, anri fully supported the staff's proposed final rule outlined in SECY-85-283.
l
~
i l
ENCLOSURE E NOV 151985 4
u .. .
13TH WATER REACTOR SAFETY RESEARCH INFORMATION MEETING The 13th Water Reactor Safety Research Information Meeting was held at the National Bureau of Standards on October 22 through 25, 1985. The meeting was sponsored by the Office of Nuclear Regulatory Research, and attended by over 600 researchers from the nuclear industry, government, and 18 foreign countries.
Some of the issues that were discussed during the 25 different sessions were:
Integral. Systems Tests The session emphasized the comparison of the detailed thermal hydraulic code TRAC, with some BWR data from the FIST loop in San Jose, California. Studies done at the University of Maryland in a small scale facility as well as comparisons as what is expected to a larger facility near completion in Ohio were also discussed. Programs in loop at PKL, ROSA IV and semiscale were also discussed. The Research challenge in this area is to further refine the concepts of scaling on integral facilities and to continue and expand international cooperation in integral systems tests.
Mechanical Structure This s.ession emphasized items such as the appropriate load combination, computer codes to calculate seismic events, the response of a steel j containment, generalized methods for calculating the dynamic response as well as the fragility of the piping systems themselves. The overall emphasis was seismic challenges to LWRs.
j Nuclear Plant Aging
,- This issue appears to be the research topic of the future. Nuclear Plant Aging seems to be growing in importance and in level of expenditures of resources.
l Issues addressed were steam generators and the role of maintenance replacement and repair in coping with so-called aging problems. A research challenge in
, this area is for more international cooperation in attempting to understand the general aging problem. The question now in this area is what safety issues or i
questions are relevant to plant aging and are we working on them at the appropriate timing and depth.
Severe Accident Sequence Analysis
~
This session placed emphasis on boiling water reactor response, and in particular how does one calculate the equilibrium power level of a BWR
- on the need and ability to do detailed fission product calculations with
! coupled codes where a systems codes such as TRAC would be coupled with a core degradation model such as MELPROG and the ensuing core damage and fission l products would be traced throughout the calculation. The need and capability ENCLOSURE E NOV 151985
to calculate in a better way hydrogen transport within containment systems and when and under what circumstances detonatable mixtures might occur were also discussed.
Separate Effects The main emphasis in this session was scaling. The separate effects mentioned and emphasized at this session included the question of liquid carryover and fallback with respect to the U tube steam generator, how to scale natural circulation, and regulatory significance on the mixing phenomena that occurs during a PTS. scenario.
Seismic Research There was an overview of the seismic research which was followed by a discussion on how does one come up with a realistic seismic hazard. The area of emphasis in this discussion was for the eastern United States. The Research challenge here is how to validate the methods used to calculate seismic risk and particular how can one produce a seismic PRA that has a high degree of acceptance and credibility.
Fission Product Release and Transport in Containment This session focused on issues relevant to severe accident questions. These issues included aerosol equipments and analyses, containment integrity, steam explosion, core concrete interaction, direct heating and debris coolability.
All of these issues are relevant to the settling and solution of the severe accident issue. ,
Equipment Qualification The equipment of interest in this session was electrical cables and battery tests. This is an area wher'e RES work should encourage and stimulate more international cooperation and produce a more realistic, basis for appraisal of equipment qualification questions.
Severe Accident Source Tenn NUREG-0956 was discussed and the theory of providing more detailed codes was voiced as a method of supplementing the approximate source term calculational procedures. There have been several efforts in the last year or so to achieve international consensus on the source term.
Primary System Integrity The items of discussion were pressure vessel steel, primary system piping and steam generators. There is a strong coupling of the question of primary system integrity with aging. It was agreed that research work should be encouraged and continued to refine and improve techniques especially in the extreme conditions thtt might be expected near the end of service life.
ENCLOSURE E NOV 151985
4 ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING NOVEMBER 15, 1985 International Visitors On Tuesday Mr. Yun Sik Kim, Emergency Planning Officer of the Korean Ministry of Science and Technology, met representatives of the IE Incident Response and Development Branch to discuss NRC's emergency response program.
On Tuesday Dr. Chen Hsing Yen, Chaiman of the Atomii: Energy Council of Taiwan; Mr. Joseph B. Kyle of the Washington Office of the American
,. Institute in Taiwan; and Mr. George Liu of the Coordination Council.for North American Affairs met with Commissioner Roberts to discuss programs
, of mutual interest.
Dr. Francisco Pascual, Chaiman of the Spanish Nuclear Safety i On Council Friday (CSN), Mr. Luis Echavarri, CSN Technical Director, and Mr. German Dominguez from the Spanish Embassy in Washington met with all five Commissioners, IP Director J. R. Shea, IP Assistant Director R. D. Hauber, and 0. E. Bassett of RES for general safety discussions.
Dr. Pascual concluded an umbrella research agreement between the CSN and the NRC with Chairman Palladino during his visit. Mr. Echavarri had a separate, earlier appointment with the EDO, RES, and IP.
=
4 4 ,
i t
ENCLOSURE G l
NOV 151985 f
OFFICE OF STATE PR0 GRAFTS ITEllS OF INTEREST WEEK ENDING NOVEMBER 15, 1985 State Program Reviews Reviews of the Alabama and Nevada radiation control programs will be conducted the week of November 18, 1985.
q-ENCLOSURE H NOV 151985
REGION III STATUS REPORT DAVIS-BESSE LOSS OF FEEDWATER EVENT NOVEMBER 15, 1985 Plant Status The plant remains in cold shutdown. The circulating water canal is drained.
~ Decay heat loop No. 2 is drained and out of service for maintenance.
1 l
J NOV 151985 ENCLOSURE L
o
[ Region III STAFF ACTIONS AS ASSIGP!ED BY W. DIRCKS MEMO 0F AUGUST 5,1985
$ 1. Item: Adequacy of the licensee's management anti maintenance activities v.
ACTION STATUS /C0094ENTS (b) Evaluate and take action on the Region III is observing maintenance activities and evaluating licensee's response to findings LER's, DVR's and other items as they relate to the control of concerning management practices maintenance. A maintenance survey team inspection conducted (e.g., control of maintenance on September 16-20, 1985 confimed previous concerns identified programs and post-trip reviews). by Region III. DRP in conjunction will DRS will assess management practices prior to restart.
- 6. Item: Reliability of the AFW containment isolation valves and other safety-related valves ACTION STATUS /C0f# TENTS (a) Monitor the licensee's trouble- Troubleshooting activities related to containment isolation shooting activities valves AF599 and AF608 are complete. Region III specialists are evaluating and monitoring MOVATS testing on other safety-
,. related motor operated valves. Of a total of 167 valves, 92 have been completed. 19 valves will require retest.
(e) Determine that the procedures for Limitorgtse operators for valves AF599 and AF608 have been adjustments of the AFW isolation adjusted and the valves have been tested under dp conditions.
valves such as torque switch bypass
- Procedure-reviews and evaluations of the training program switches are clear and proper, and will be corpleted prior to restart. Confirmatory testing that associated training programs are will be performed during startup.
adequate._ Confirm that adjustment settings ~are consistent with plant procedures. ,
c, 4
P ,- -
0 i E
F . .*
2
p* s
~
Y
)
- 7. Item: Adequacy of emerge,ncy notifications _
g' '
me
~-
SE ACTION STATUS / COMMENTS ca (a) Verify the adequacy of the licensee's Investigation of the adequacy of the licensee's procedures US procedures and training for the report- and training for the reporting of events to the NRC EE ing of events to the NRC Operations Operations Center has been completed. One violation of NRC Center. requirements was found. Inspection results are documented in Inspection Reports 85023 and 85034. IE Information Notice 85-80 was issued dealing with timely declaration of Frergency Class, implementation of an Emergency plan, and Emergency Notifications based in part on the findings and conclusions derived from the Davis Besse June 9, 1985 event.
Reliability of AFW pump turbines
- 8. Item:
ACTION STATUS / COMMENTS (a) Monitor the licensee's trouble- Troubleshooting activities are complete. Region III shooting activities including will monitor confirmatory testing during plant startup possible hot plant operation to as part of startup test activities.
confirm failure mode.
(d) Verify that the AFW system has been Results of test review group meetings have culminated adequately tested to confirm system in the development of a charter outlining test review group configuration involved with design responsibilities and activities. AFW testing will be basis events. included as part of the testing review team effort.
(e) Review the implementation of the The licensee is developing a training program on resetting operator training program to assure of the trip throttle valve. This training will include proper operator actions, such as resetting of trip mechanism at operating conditions, resetting of trip throttle valve. therefore, the training will be completed during plant '
restart.
E .
p 3 .
55 m
r-
< 3
se 9. Item: Reliability of the PORY -
E g ACTION STATUS / COP 9 TENTS en rs (a) Monitor the licensee's trouble- Troubleshooting activities have been completed. Confirmatory 83 shooting activities testing will be conducted at operating temperature and pressure. Testing of an equivalent valve indicated a lower flow condition than expected. Flow results from Crosby (valve manufacturer) testing were higher than the flow results.from the Marshall Steam Station test facility. All test data indi-cated flow was less than expected. Additional flow testing at the Marshall Steam Station facility is planned for November 15, 1986.
s
- 12. Item: Resolution of equipment deficiencies ACTION STATUS / COMMENTS (a) Monitor the licensee's trouble- All the Region III activities relative to '
shooting activities troubleshooting / root cause activities have been completed and are docunented in Inspection Reports85-021, 85-022 and 85-025.* -
s 9
P 8
gi
- Inspection Report 85025 is in draft and will be issued in approximately I week.
r-4
Other Activities Installation of the new electric motor driven startup feedwater pump (SUFP) is completed. Hydrostatic testing of the system piping was successfully performed this week and testing of the moter (uncoupled from the pump) is scheduled for November 15, 1985. A regional NDE specialist reviewed welding records and material test reports to. piping used in th. SUFP system. Calibration of the associated instrumentation and testing of the system is in progress.
Evaluations and inspections of 2155 safety system piping supports are continuing.
Nonconformance Reports (NCRs) have been written against 1916 of 2099 pipe supports inspected so far. Rework is required on 141 of the 872 supports that have been evaluated by the licensee's engineering department. Rework has been completed on 23 supports. There are 16 licensee inspection teams working on this project.
M0 VATS testing continues on the 167 safety-related motor-operated valves onsite. Of the 120 valves reported completed last report, oCy 92 were completed. Approximately 19 valves will require retesting due to maintenance activities. The licensee is now repairing and testing valve motor operators continuously with three overlapping ten-hour shifts.
The NRC test review group has completed the preliminary review of the licensee's SRTP with satisfactory results. The draft Technical Evaluation Report (TER) has been sent to NRR. A final TER is anticipated by the end of November, subject to the licensee's schedule. The review team will continue to provide weekly coverage of licensee testing activit'es. The licensee's schedules show this effort complete by February 2,1986. The test review group has assessed the licensee's schedule and concluded that completion in early March, 1986, is more realistic.
During the review of the Control Room Emergency Ventilation System as part of the SRTP, the licensee determined that existing system tests did not adequately address the operability of the system cooling function. Region III is evaluating the significance of this matter.
N OSURE L NOV 151985 5
4 DEPUTY EXECUTIVE DIRECTOR FOR REGIONAL OPERATIONS AND GENERIC REQUIREMENTS (DEDROGR)
Week Ending November 15, 1985 CRGR Attached is a summary of the CRGR activities for the period September 1 through October 31, 1985. Background material on topics reviewed by the Committee and the minutes of CRGR meetings are sent to the Commission. Copies are provided to the Public Document Room after the NRC has considered (in a public forum) or decided the matter addressed by the documents. Questions concerning this monthly report should be referred to Walt Schwink (492-8639).
ENCLOSURE M NOV 151985
Data: November 15,1985 g age 1 of 3 SUMARY OF CRGR ACTIVITIES o
- (September 1 through October 31,1985)
~
CJT
$ Meeting No.
Mesting Date CRGR Recomendation CRGR
. (Announcement- Status to EDO EDO Action i Date) Agenda t i
Complete CRGR recomended that the No action required at 82 Review, Proposed Final this time because NMSS Version of the Insider proposed final rule be 10/23/85 issued after modification has not yet taken a Rules position on the CRGR to reflect CRGR coments.
recomendations.
-Sponsoring Office - NMSS
-Category 2 Item
! reflect CRGR concerns l Bulletin, Motor-0perated the proposed bulletin after modifications are made to. and issued.
Valve (MOV) Common Mode Failures During Plant reflect CRGR recommendations.
Transients Due to Improper These modifications should be Switch Settings coordinated with the ROGR staff prior to issuance of
-Sponsoring Office - IE the bulletin.
-Category 2 Item
-Issue #129 No action required at Review, Proposed IE Comolete CRGR recomended that the Commission Paper on Comission Paper be approved this time because IE subject to modifications. has not yet taken Alternatives for Offsite a position on the CRGR Emergency Medical Services These modifications should be coordinated with the R0GR staff. recommendations.
_ Sponsoring Office - IE
-Category 2 Item m -Issue #124 M
1 U?
E m
3
Page 2 of 3 Date: N:vember 15, 1985 se
SUMMARY
OF CRGR ACTIVITIES Sg (September 1 through October 31,1985) em en m Menting No.
S ating Date .
CRGR CRGR Recommendation (Announcement EDO Action Date) Agenda Status to EDO 4
1 81 Briefing, Existing and Complete CRGR offered comments concerning No action required at 9/25/85 Forthcoming Guidance decommissioning guidance and this time.
Associated with Decom- requested that all decommissioning
_ Sponsoring Office - RES review is necessary.
-Category 2 Item-
-Issue #126 Review, Proposed Rev. 2 Pending CRGR recommended prompt issuance No action required.
to Regulatory Guide 1.99, of the proposed Rev. 2 to RG 1.99 Radiation Damage to Reactor for public comment. ,
Vessel Materials
_ Sponsoring Office - RES
_ Category 2 Item
_ Issue #121
- Review, Proposed RG, " Guide Pending CRGR recommended issuance of the No action required at for Licensee Preparation and proposed RG 1.XXX for public this time because NRR
! has not yet taken a J NRC Staff Review of Plant- comment after satisfactory Specific Analysis Required by resolution of CRGR concerns. The position on the CRGR the Pressurized Thernal Shock CRGR Chairman asked that he be recommendation.
Rule, 10 CFR 50.61 provided with a copy of the revised RG before it is issued.
-Sponsoring Office - NRR
-Category 2 Item
-Issues #127 se ______________________________________________ .._________________________________________________________
P S?
!5, r
3
Page 3 of 3 Date: November 15, 1985 4
j[
SUMMARY
OF CRGR ACTIVITIES
-c (September 1 through October 31,1985) 4 rm v1 S$MeetingNo.
4 " Resting Date (Announcement CRGR CRGR Recommendation Date) Agenda Status to EDO EDO Action 81 Review, Proposed IE Complete CRGR recommended issuance of the- Bulletin modified to (Continued) Bulletin " Steam Binding of Bulletin after modification to reflect CRGR concerns i Auxiliary Feedwater Pumps reflect CRGR comments and recom- and issued.
mendations.
-Sponsoring Office . IE 4
-Category 2 Item
-Issue #128 80 Briefing, Proposed Commission Pending No CRGR recommendation necessary None required at this 9/9/85 Paper Concerning Offsite at this time. CRGR will review time Medical Services this item at a future meeting.
f
-Sponsoring Office - IE
-Category 2 Item
-Issue #124 Review, Proposed Resolution Complete CRGR recommended approval after Approved and forwarded of USI A-43, " Containment modification to reflect specific to the Commission.
Emergency Sump Performance CRGR concerns and recommendations.
-Sponsoring Office - NRR
-Category 2 Item
-Item #47 Briefing, Resolution of Public Pending No CRGR recommendation necessary None required at this Comments on Proposed Final at this time. The CRGR will time.
rg Rulemaking on 10 CFR 55, review this item at a future g2 " Operators' Licenses" and meeting.
g; Three Related RGs C
55 -Sponsoring Office - NRR
- -Category 2 Item
-Item #125
ITEMS ADDRESSED BY THE COMMISSION'- WEEK'ENDING NOVEMBER 15, 1985 A. STAFF REQUIREMENTS ~ DISCUSSION'0F EXEMPTION REQUESTS - ENVIRONMENTAL QUALIFICATION, 2:00 P.M., TUESDAY, NOVEMBER 5, 1985, CIMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to W. Dircks dated 11/15/85 The Commission met with staff and representatives of Northeast Nuclear Energy Company (NNECO) to discuss the environmental qualification (EQ) extension of the November 30, 1985 deadline for Millstone Unit 1 (SECY-85-345).
The following persons participated in the meeting:
John F. Opeka Senior Vice President NNECO Nicholas S. Reynolds Legal Counsel to NNECO Richard Kacich Manager of Facility Licensing NNECO Commissioner Asselstine requested staff to provide a note to the Commission identifying any instances in which the staff might have made a recommendation regarding extensions of the h vemiser 30, 1985 deadline for environmental qualification on the basis of benefit-cost analyses.
(NRR) (SECY Suspense: 11/22/85) i Chairman Palladino requested Commissioners to provide their votes on SECY-85-345 to the Secretariat no later than noon, Thursday, November 7.
(OCM)
(Subsequently, the Commission voted 3-2 (with Chairman Palladino and Commissioner Asselstine approving) to disapprove the staff recommendation in SECY-85-345 to deny the ext;ension request.)
' ENCLOSURE O NOV 151985
3 2
B. STAFF REQUIREMENTS - BRIEFING ON~NUMARC INITIATIVES, 9:30 A.M., WEDNESDAY, NOVEMBER 6,1985, COPNISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) Merao SECY to RECORD dated 11/15 The Commission met with representatives of the Nuclear Utility Management and Human Resources Committee (NUMARC) to be briefed on NUMARC initiatives regarding fitness for duty, engineering I
< expertise on shift, maintenance and technical hardware issues. l The following persons participated in this briefing:
- l l
J.H. Miller, Jr., President Georgia Power Company l
and '
Chairman, NUMARC Steering Committee Warren Owen, Executive Vice President puke Power Company and
__ and Vice Chairman, NUMARC Steering Committee C.b. Woody, Vice President of Nuclear Operations Florida Power and Light
, and Chairman, NUMARC Working Group'on Maintenance (NUMARC requested that the Commission defer decision on SECY-85-163A, Station Blackcut (USI-A44), until February 1986, at which time NUMARC input will be provided.)
4 There were no requirements at this meeting.
C. STAFF REQUIREMENTS - PERIODIC MEETING WITH ADVISORY COMMITTEE ON REACT SAFEGUARDS ( ACRS), 2:00 P.M. , THURSDAY, NOVEMBER 7,1985, C0fEISSIONERS' EDNFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to R. F. Fraley dated 11/15/85 The Commission met with the Advisory Committee on Reactor Safeguards (ACRS) to discuss the impact of severe environmental phenomena on off-site emergency planning, and to receive a --
brief status report on ACRS activities regarding safety goals and the ACRS effectiveness report.
Chairman Palladino suggested that the ACRS revise the sentence ple, plant designs to withstand the impacts beginning
... as low "For as exp/
10
~
year." on pages 1 and 2 of the October 16, 1985 letter from D. Ward to Chairman Palladino ("ACRS Report on Impacts of Natural Phenomena on Off-Site Emergency Response") .
ENCLOSURE O
! NOV 151985 1
l
5 N
c.n NRR HEETING NOTICES
- h DOCKET APPLICANT /
DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 11/18-19/85 50-245 Millstone Site Review M-1 IPSAR, ISAP, and ACRS J. Shea Waterford, Conn. FTOL-SER Conversion Northeast Nuclear Energy Co.
11/19/85 50-361 MNBB-6507 To discuss Core Protection Combustion Engineering H. Rood 9:00 am 50-362 Bethesda Calculator Improvement Program CPC Owners Group ORNL 11/19/85 MNBB-6110 To discuss Davis-Besse restart NRC Staff J. Stolz 2:30 pm Bethesda SER 11/19-20/85 50-601 Westinghouse To discuss PRA submitted by Westinghouse C. Patel 8:30 am Nuc. Energy Ctr Westinghouse in RESAR-SP/90 BNL Monroeville, PA 11/19-20/85 50-445 P-422 To discuss Supplemental Safety Citizens Assn. for A. Vietti-Cook 9:00 am 50-446 Bethesda Evaluation Report Mos. 7-11 Sound Energy 11/20/85 50-219 P-114 To discuss long range planning GPU Nuclear Corp. J. Donohew 9:30 am Bethesda to complete deferments from Cycle 11R outage in the operating Cycle 11 - Dyster Creek 11/20/85 50-443 PSNH-NHYD Off. To discuss Instrumentation & Public Service Co. V. Nerses 8:30 am 50-444 7910 Woodmont Controls review of New Hampshire i Bethesda l ..
l 11/21/85 50-400 Shearon Harris Environmental qualification Carolina Power & B. Buckley 3:00 pm g Site audit Light Co.
E l E A
Copies of Tummaries of these meetings will be made publicly available and placed in the respective docket file (s) in the NRC and local public document rooms.
g ,
>A
$ NRR MEETING NOTICES
- NOVEPEER 15, 1985 DOCKET APPLICANT /
DATE/ TIME NUlWER LOCATION PURPOSE ATTENDEES NRR CONTACT 11/18/85 50-220 P-110 Discussion of inspection and Niagara Mohawk Power R. Hermann 9:00 am Bethesda possible corrective actions for stub tubes that may be identified as degraded following inspection 11/18/85 50-331 P-110 Effect of leakage from purge / Iowa Elec. Light & M. Thadani 1:00 pm Bethesda vent valve inflatable seals on Power Co.
containment oxygen concentration 11/18/85 50-410 P-422 To discuss Caseload Forecast Niagara Mohawk Power M. Haughey 1:15 pm Bethesda and Schedule for Nine Mile Point 2 11/18/85 50-302 P-118 To discuss AFW reliability and Florida Power Corp. H. Silver 1:00 pm Bethesda related staff activities
- C pies 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 l
1 m l
P l 8
=
m T
t
NMSS MEETING NOTICES _ , .
FOR WEEK ENDING: 11/15/85 2
g Divisi:n of Fuel Cycle cnd Material Safcty- ,
5 DOCKET ATTENDEES /
APPLICANT NRC CONTACT NUtWER LOCATION PURPOSE gDATE/ TIE 11/21/85 70-135 Apollo, PA To discuss questions and concerns Nina Toms (ADM) Crow related to Babcock & Wilcox (Apollo) Jerome Roth (RI) operations.
W. Kushner (RI) ,
P. Loysen (FC)
W. Crow (FC)
G. Johnson (ELD)
Cindee Virosteek (citizen) 11/22/85 Washington, Discussion of medical waste with C. Lively (ACNP) Cynningham 2:00 DC member of the American College R. Cunningham (FC) of Nuclear Physicians (ACNP). L. Roche (FC) 11/22/85 Willste To discuss dry storage of spent fuel A. Onodera (Hitach'i Roberts .
4:30 5th floor with Hitachi Zozen. Zozen) -
conf room J. Roberts (FC)
- F. Sturz (FC)
J.Schneider(FC) 11/25/85 Willste To discuss submittal of topical Reps of Foster Wheeler Roberts 10:00 Room 540 report early next year for dry and General Electric storage of spent fuel, of United Kingdom J. Roberts (FC)
F. Sturz (FC)
J. Schneider (FC) i 12/4/85 Bal timore, Presentation at Johns Hopkins R. Cunningham (FC) Cunningham
.l 8:30-5:00 MD University - Seminar on Low-Level -
(date changed) Waste - Under the auspices of CARER.
Division of Safeguards None
$ Division of Waste Management r-None y 5
o
-- - -~ --- - .
. = _ ..
1 -
5 l [ RES MEETING NOTICES November 15. 1985-i
, "3 DOCKET ATTENDEES /
i
- LOCATION DATE/ TIME NUPEER PURPOSE APPLICANT NRC CONTACT NAS Board Room Meeting of the Comittee on Nuclear N Minogw ,
11/21/85
, 10:00 AM 2101 Constitution Safety Research to discuss the future i Avenue, NW of the nuclear safety research program, omftp ee l 11/22/85 P-110 Meeting with AIF and Grove Engineering NRC Arlotto 8:30 AM to discuss potential interaction staff on plant life extension. AIF/ Grove Engineering (Rowden/
Feinroth et al) i
- 11/25-29/85 Tokyo /Tokai, To attend Japanese Atomic Energy Steyer
! Japan Research Institute Decomissioning i Workshop and present NRC j decomissioning activities status I
1
) .
I 9 -
- p i 8 i
E m
T
{
, n November 15,.1985
.g 6-6 en RII MEETING NOTICE M
i DOCKET ATTENDEES /
PURPOSE APPLICANT NRC CONTACT DATE/ TIME NLMBER . LOCATION ,
RII Office Duke Power Company - Selected RII and Walker 11/19/85 10:30 am Catawba - SALP Board NRR staff members Meeting i
2 P
J 8 E
m "U
- - -