ML20138S077
| ML20138S077 | |
| Person / Time | |
|---|---|
| Issue date: | 11/13/1985 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-851108, NUDOCS 8511190494 | |
| Download: ML20138S077 (57) | |
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l I November 13, 1985 .
4 For: The Comissioners ,
q i j From: T. A. Rehm Assistant for Operations, Office of the EDO ;
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING NOVEMBER 8, 1985 f
) A sumary of key events is included as a convenience to those Commissioners
! who may prefer a condensed version of this report.
Contents Enclosure i Administration A Nuclear Reactor Regulation B Nuclear Material Safety and Safeguards C ;
Inspection and Enforcement D :
l Nuclear Regulatory Research E
! Executive Legal Director F*
l International Programs G l
State Pr w ams H
,' Resource Management I i Analysis and Evaluation of Operational Data J' f
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! Small & Disadvantaged Business Utilization & Civil Rights K*
- Regional Offices L f CRGR Monthly Report M*
Executive Director for Operations N* [
l Items Addressed by the Comission 0 !
! Meeting Notices P (
Proprietary or Other Sensitive Information (Not for Q !
! externaldistribution) !
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- No input this week. 2 II l Y T. A. Rehm Assistant for Operations !
m,ly fl3 pg Office of the Executive Director i for Operations ;
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Contact:
T. A. Rehm, ED0 f 492 7781 i 4
6 l ', HIGHLIGHTS OF WEEKLY INFORMATION REPORT f'
l WEEK ENDING NOVEMBER 8, 1985 l
j Grand k 1f, Unit 1 l
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! The licensee has identified numerous crack-like indications on the
! surface of a cross-shaped assembly which connects the recirculation !
Jump discharge piping (24-inch diameter) to the jet pump ring supply ,
J weder (16-inch diameter). The crack indications are circumferentially ;
J located within a 6-inch band above the weld connecting the cross - ;
! assem6ly to the discharge piping and within a 7-inch band below a' weld ,
i connectint the cross assembly to a cap. The indications are generally 1 3/4 inch ong and 1/4 inch deep, except one indication which s 3 1/2 !
4 inches long. The wall thickness of the cross assembly in the region of
- the cracks is greater than 2 inches.
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! Grand Gulf Unit 1 is in a planned outage which began October 12 and is scheduled to end November 24. One of the tasks being performed is t i Induction Heating Stress !sprovement (IH5!) of selected welds in the .
! recirculation piping, including the welds adjacent to these crack l
! indications. Licensee believes the crack indications are associated 2
with, and may have been caused by, the INSI process. Licensee is - i evaluating the situation, including grinding of the crack indications. l 2
i Microbiologica11Pinduced Corrosion - Comanche Peak 1 and 2 l s
! Evidence of microbiologically-induced corrosion has been found in the i fire protection system, particularly at fittings. Some pipe / fitting l
replacement any be required. The system is currently filled with water i from the Squaw Creek Reservoir, which is high in dissolved minerals. ;
Texas Utilities Generating Company is investigating the extent to which i the problem may exist in other systems. Colonies of bacteria have been i
found in the r'esctor water makeup tank for Unit 2. Unit 2 i i domineralized water sources are separate from Unit 1 no problems on '
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Unit I have been found thus far. The problem is believed to be j confined to stagnant systems. The Applicant will be issuing a report i
in the near future.
i j Dry Seent Fuel $torens i As reported previously, during an unlicensed demonstration at the Idaho i NationalEngineeringLaboratory(INEL) cracks were observed in non-structural i
! .weldsinthefuelbasketoftheGeneralNuclearSystems,Inc.(Mll) CASTOR '
l V/21 nodular cast iron dry spent fuel storage cask. On October 31, 1945, a j meeting was held between MSI and MS$ staff. MSI examination and analyses
- to date suggest that the cracks were caused by thermal stress due to storing ,
i fuel with a heat lead (about 28.4 kW) beyond the design basis lead (21 kW) 'n
- a basket fabricated with less margin for expansion (i.e., a tighter fit to r
! attain prester thermal efficiency and to permit precise positioning of thermo-
! couple eads for the test) than specified in the CASTOR V/21 design submitted to NRC. MS! will submit a preliminary report concerning the INEL occurrence
! in November 1936. NRC staff will esamine it and meet again with MSI.
ON$1 will submit a second and probably
' Assuming final reportresolution to NRC. At of this time metter,it appears the cracks do not compromise the
- basket storage capability er safety and that future basket fabrication j tolerances can be assured to eliminate the problem.
! NOV 819H
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0FFICE OF ADMINISTRATION
- Week Ending November 8, 1985 1
ADMINISTRATION OF THE FREEDOM OF INFORMATION ACT
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STATUS OF REQUESTS i )
1 Initial Appeal of ;
} Request Initial Decision i Carryovers, 1984 179 23 Received, 1985 740 41 j Granted 584 30 j Denied 170 16 ,
Pending 165 18 '
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3 ACTIONS THIS WEEK Received
{ Susan L. Hiatt, Requests copies of all records regarding the meeting i OCRE between NRC and the Hydro en Control Owners Group held L (85-728) on or about September 5, 985. i
! Ellyn R. Weiss, Requests copies of the NRC's inspection report and ;
i Harton, Weiss & related records regarding the system evaluation of the l i Jordan auxiliary feedwater system at Turkey Point Units 3 and 4. l 4 ,-(85-729)
'Ron Kucera, Requests a copy of the license app 1tcation filed by t
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State of Missouri R.M. Wester and Associates and subsequent correspondence !
(85-730) between the applicant and NRC. i John Harrison, Re uests DOE /NRC Forms 741 regarding shipments of nuclear The Columbian fuel entering the US via Oregon and Washington from 1970 t
! (85-731) through October 1985. (
i i (Anindividual Requests records relating to an incident at Kelly Air
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requestingrecords) Force Base on July 19,1985.
l (85-732) l Cindee Virostok, Requests copies of specified records relating to BAW
- Kiski Valley facilities in Apollo and Parks Township, Pennsylvania, i Coalition i (85-733) l Joel M. Kaplan, Requests copies of procedures, rules, and regulations in
' Karlin and Fleisher effect in 1973 through 1976 regarding radiat'on exposure '
(85-734) of persons working in the Zion nuclear power plant, j CONTACT: J. M. Felton j 492 7211 i 1 i i
[NCLOSURE A r N
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' 2 Received, Cont'd John E. Ryan Requests a copy of Ol's report on Nine Mile Point Unit 2 (85-735) relating to nuclear auditor harassment.
Susan L. Hiatt, Requests copies of four categories of records identified OCRE in Enclosure E of NRC's 9/27/85 Weekly Information ,
(85-736) Report.
Steven Aftergood, Requests all records relating to an IAEA meeting on Committee to October 9-11, 1985, in Vienna, Austria, "IAEA Technical Bridge the Gap Conunittee Meeting on Preparatior of Guidebooks on (85-737) Conversion of Research Reactors from High to Low Enriched Uranium Fuels."
- Steven Aftergood, Requests any written materials submitted to the NPC in Committee to response to the show cause orders by any of the 31 ~
Bridge the Gap affected licensees or other interested persons regarding (85-738) why excess HEU fuel should not be removed from research and test reactors and critical experimental fact 11 ties.
Donald K. Slingsby, Requests copies of four specified records relating to Proto-Power / Bisco Alaron, License No. 32-20826-01.
Nuclear, Inc.
(85-739)
James F. Nicolosi, Requests copies of all records relating to inspections in Hydro Nuclear October 1984 January 1985, and June 1985, and any Services subsequent inspections regarding North American (85-740) Inspection Inc.
. . Granted
- Stephen H. Hanauer, In response to a request for all training manuals and Technical Analysis other technical references and instructional records Corporation used at the NRC Training Center, made available 30 (85481) records. Informed the requester that some training manuals were already available at the PDR.
Richard E. Webb, In response to a request for 14 categories of records Studies of Nuclear relating to the Davis-Desse nuclear power plant, informed Hazards and the requester that 18 records subject to this request Constitutional are already available at the PDR.
Law (85-611)
Charles Barnes In response to a request for all records from June 25, (85644) 1975, tr. March 1, 1976, relating to a waste shipment Nevada, burial site from the Cimarron at the Beatty,lity, plutonium faci as described in IE Dulletin 75 07, made available five records.
ENCLOSURE A NOV 6 Ud5
3 i Granted, Cont'd 2 Frank Ruswick, In response to a request for three categories of records West Michigan relating to a request by Consumers Power Company to Environmental leave in place radioactively contaminated soil at the Big Action Council Rock Point nuclear power plant, made available four (85-650) records. Informed the requester that five additional records subject to this request are already available at the POR.
Patricia Hainer in response to a request for records concerning Serono (85-681) Diagnostics, License No. 201593001, made available 14 records.
Louise Ponce In response to a request for eight categories of records (85-684) relating to radioactive materials and waste at the Stepan I Chemical Company in Maywood, New Jersey, made available six records. Informed the requester that four additional
' records subject to this request are already available at ;
the POR.
Lila Pope In response to a request for copies of records concerning (85-702) each misadministered dose from New Center Radiology, Detroit, Michigan, informed the requester that the NRC could not locate any records subject to this request.
David S. Palmer, in response to a request for copies of " Evacuation Time ERP&M Estimates for the Plume Exposure Pathway EPZ at TMI,"
(85707) dated March 3, 1983, any amendments or updates, and all appendices or addendum to the report or its amendments or updates, made available a copy of the requested report.
- - Informed the requester that NRC could not locate any other records subject to this request.
L Oented Scott Faust, In response to a request for a copy of the transcript of The Wichita Eagle- the Comission briefing held on June 3,1985, which
,l Beacon preceded the licensing hearing for the Wolf Creek nuclear j (85-701) power plant, informed the requester that two transcripts are already available at the POR. Denied portions of one transcript pursuant to Exemptions 5 and 7 of the Government in the Sunshine Act.
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EHCLOSURE A NOV 8 1985
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.l l WEEKLY INFORMATION REPORT ,
l DIVISION OF CONTRACTS l
WEEK ENDING NOVEMBER 8, 1985 1 :
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! RFP ISSUED 1
3FP No.: RCl-86-31i
Title:
" Technical Support for Non-Destructive Examination Van"
Description:
On a task order basis, the contractor shall provide personnel with .
4 expertise in the field of non-destructive examination and a I l radiographic isotope source to perform field non-destructive l
'. examinations at nuclear power plants under construction or in t 2
operation anywhere in the United States. :
Period of Performance: Twenty-four months l Sponsor: Region 1. Division of Reactor Safety i Status: RFP issued on November I, 1985. Proposals due on December 2, 1985.
i RFP No.: RS-ORM-85-335 !
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Title:
" Integrated Library System" l'
Description:
Software maintenance, support and timesharing services for the Integrated Library System (ILS) as instal lsd and subsequently !
enhanced. ;
Period of Performance: 2 years with I option year
- Sponsor Office of Resource Management ,
Status: RFP issued on November 6, 1985. Proposals due December 6, 1985.
] l j RFP No.: RS-ORM-85-336 !
j Titlet "ADP Information Technology Support Center Contract" l i Descriptions End user computing support services for users of NRC l
} . , microcomputers and NRC users of the NIH computer facility. !
) Period of Performance: 2 years l j - Sponsor Office of Resource Management
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Status: RFP issued on November I, 1985. Proposals due December 3, 1985. t l PROPOSALS UNDER EVALUATION RFP No.: RS-RES-86-104 F
Title:
" Cooperative Human Reliability Evaluation Program" I Description Compare and contrast NRC and EPRI analytic tools for conducting
{ human reliability analysis with those of other participating j nations to assess the current state-of-the-art and to guide ;
J future research.
) Period of Performance 12 months j Sponsor Office of Nuclear Regulatory Research !
i Status RFP closed on October 30, 1985. Proposals forwarded to source i j Evaluators for review on October 31, 1985. '
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[NCl.0$URE A ,
NOV 819H i
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Div'ision of Contracts '
Weekly Information Report s PROPOSALS UNDER EVALUATION (cdnt'd)
-[' RFP No.: RS-ADM-85-235
Title:
"NRC Translation Services"
Description:
The contractor will be required to furnish translation services for reports and other related material provided by NRC when issued by a formal work order.
Period of Performance: 2 years Sponsor: Office of Administration / Technical Information & Document Control Status Negotiations completed on November 5, 1985. Best and final offers due on November 12, 1985.
RFP No.: RS-0ZE-d5-15E
Title:
"n.iC Training f.ourses for Inspectors and Engineers"
Description:
The contenetor will provide experienced instructors and other experts to donduct two training courses of 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> duration each. One course shall be' titled, " Electrical Technology and Codes," the other " Instrumentation Technology Codes."
Period of Performance: One year with 3 one ysar options Sponsor Office of, Inspection & Enforcement * /
Status: Best and hnal Offers received on November 7, 1985 and forwarded to Source Evaluators for review on November 7, 1985.
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CONTRACT AWARDED ;
' RFP No.: RS-ADM-86-211
, Tit le's " Newspaper Clipping Service"
Description:
The contractor shall provide relevant news articles from local
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and national newspapers for incitiJion in the NRC "Hedia Monitor".
Period of Performance: 2 fears Sponsor Office of Administration Status: Pixed Price Requirements Contract No. NRC-10-86-2ll awarded to Press Intelligence Inc. In,the amount of $69,120.00, effnetive November I, 1985.
CANCEll.ATION y RFP No.: RS-NMS-85-001 -
Title:
" Development of Regulstory Ef fectivenc6 Review (RER) Team Training Guides" ,
Description:
Development of detailed guldsoce and instructional materials
~. , to be used in tralning NRC ualf to conduct safeguards regulatory effectiveness reviews.
Peiled of Performance 2 years,, ,
Sponsori- Of fice of Nutissr Matet ta', Safety and Sgfeguards Status: RFP cancelled on Noernber 7,1985. ,
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O Division of Contracts Weekly Information Report ADMINISTRATIVE MATTER The protest filed by Compt'com Security, Inc., on August 16, 1985 against revised RFQ 0001, Mod. I was dismissed with prejudice by the General Servides Board of Contract Appeals on October 22, 1985. NRC and Compacom settled the protest and jointly requested dismissal of the protest.
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l EtlCLOSURE A NOV 8 1985
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OFFICE OF NUCLEAR REACTOR REGULATION i
. ITEMS OF INTEREST Week Ending November 8, 1985 I i
Fort Calhoun Station Unit No. 1 The Fort Calhoun Station is currently in a refueling outage. The
- licensee just completed eddy current testing of the steam generators tubes. The licensee tested 958 tubes in the A steam generator and 965 tubes in the B steam generator. Eighteen tubes in the A steam i generator and seventeen tubes in the steam generator were considered to be degraded; no tubes were considered to be defective. All but three
! tubes were considered degraded because the eddy current probe would not pass thru the tubes.
The licensee eddy current tested 9925 tubes out of 10,010 tubes in
, mid-1984. Only n'ine tubes were considered degraded because the probe would not pass.
The' significance of the above information is that denting appears to be progressing in the continued dentingould c, Fort resultCalhoun in leaking Stationtubes, steam it isgenerators. Although not expected to result in a tube rupture.
Grand Gulf Unit 1 t,
' The licensee has identified numerous crack-like indications on the surface of.a cross-shaped assembly which connects the recirculation sump discharge piping (24-inch diameter) to the jet pump ring supply leader (16-inch diameter). The crack indications are circumferential1y
- located within a 6-inch band above the weld connecting the cross i assembly to the discharge piping and within a 7-inch band below a weld
! - connecting the cross assembly to a cap.. The indications are generally
, 3/4 inch long and~1/4 inch deep, except one indication which is 3 1/2 inches long. The wall thickness of the cross assembly in the region of -
t the cracks is greater than 2 inches.
Grand Gulf Unit 1 is in a planned outage which began October 12 and is scheduled to end November 24. One of the tasks being performed is Induction Heating Stress Improvement _(IHSI) of selected welds-in the
. . recirculation piping, including the welds' adjacent to these crack indications.. Licensee believes the crack indications.are associated with, an6 may have been caused by, the IHSI process.- Licensee is evaluatinithesituation,includinggrindingofthecrackindications.
! ENCLOSURE B NOV 8.1985 f --- m-. ..m, .
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Limerick
'On October 28, 1985 the Licensing Board issued an Order in response ~to the Appeal Board's remand of the PID-2 onsite emergency planning
, back-up medical arrangements issue. The Order requires an applicant ,
response to the issue by November 18, a response by the intervenor and
-the Commonwealth.of Pennsylvania by December 2 and a response by the
- staff by December 12. The Order did not specify any other action other than submittal of the responses.
On October 24, 1985 the Appeal Board issued an Order that specified i that oral argument on the appeals by intervenors Air and Water Pollution Patrol and the Graterford inmates from the Fourth Partial
! Initial Decision will be held on December 4, 1985. PID-4 concerned off site emergency planning for the inmates at the State Correctional Institute at Graterford, PA.
Limerick Unit 1.is at 69% (664 MWe) power and is conducting feedwater i system tuneups.
1 Rancho Seco Startup
! The' Rancho Seco Nuclear Generating Station attained criticality at 10:48 p.m.- PST.on November 2, 1985, and as of 11:50 EST on November 4,
.1985, the plant was stabilized at 43% power. The plant will remain at j approximately 40% power for several days while auxiliary boiler repairs
! are in progress. A main turbine generator trip test will be performed
.- prior to increasing power to 100%. .
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_ The startup followed resolution by the Sacramento Municipal Utility ion V. The NRC District (SMUD)were safety concerns of safety raised concerns followingraised by NRRofand the analyses p Reg' ant transients which occurred during an unplanned shutdown'from 15% power on October L 2, 1985. Prior to restart, SMUD was required to modify the automatic
- ' start circuitry for-the auxiliary feedwater (AFW) system. The AFW initiation circuitry modification was required after it was determined that during the October 2, 1985 transients, mequal action by the operators was necessary to initiate AFW flow.
- In addition to AFW system hardware modifications, SMUD completed evaluations to resolve other shutdown related concerns. These involved the main feedwater: system, secondary plant vacuum, the high pressure
- injection system, and primary plant cooldown. SMUD also committed to expedite AFW related Technical Specification changes and to evaluate the feasibility of accelerating the schedule for upgrading the AFW l control system.-
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ENCLOSURE B NOV S1935
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Comanche Peak 1 and 2 Microbiologically-induced Corrosion Evidence of microbiological 1y-induced corrosion has Some been found pipe in the
/ fitting fire protection system, particularly at fittings.The system is currently filled with w replacement may be required.from the Squaw Creek Reservoir, which is high Texas Utilities Generating Company is investigating the extent to which
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the problem may exist in other systems. Colonies of Unit bacteria have been 2
found in the reactor water makeup tank for Unit 2.
demineralized water sources are separate from Unit 1; no problems on
- The problem is believed to be Unit 1 have been confined to stagnant systems. found thus far.The Applicant will be issuing a report in the near future.
Asiatic Clams Asiatic clams are now present in the Squaw Creek Reservoir. They have been found in the service water intake structure and in one component The cooling heat exchanger (which has not been in service recently).
service water system has been realigned to eliminate any stagnant portions. The Applicant is updating its response to the I&E Bulletin
,on this subject.
t ENCLOSURE B NOV 8 1985
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4 Point Beach Nuclear Power Plant, Unit No. 2 The staff was notified that during visual inspection of fuel assemblies .
- removed from the core during the current refueling outage, the licensee !
identified two fuel assemblies in a degraded condition. Some fuel rods showed signs of erosion and at least one fuel rod was severed. In the .
- case of the severed fuel rod, fuel pellets were released. I The licenset determined that the fuel rod problems were due to baffle jetting similar to that experienced previously on Unit 1. The licensee
, is evaluating corrective actions but the corrective actions will not be completed until the next outage. The staff will evaluate whether it is .
acceptable to resume operations before all the corrective actions are completed. ;
i St. Lucie Plant, Unit No. 1 l
At approximately 8:30 a.m. on November 6, 1985, we were informed that activity associated with the St. Lucie Plant, Unit No. 1 Cycle 7
- refueling outage had been stopped. During the night the lifting device j was attached to the upper guide structure and the lift was started.
Before completing the lift it was discovered that the upper guide i structure was tilted. Investigation revealed that one of the three
- bolts used to secure the upper guide structure to the lifting device
! was not properly secured and the upper guide structure was being
- supported by only two bolts. Based upon our concern that failure of these two bolts might allow the upper guide structure to fall causing fuel damage, the licensee issued an unusual event report at 10
- 45 a.m.,
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'pending the results of an engineering analysis of the situation.
- In a 3:00 p.m. conference call that involved the site management and
- Region II, the licensee informed the NRC that he is in process of developing an independent system to support and remove the upper guide structure and attached lifting device. The design of this independent support system is expected from the NSSS vendor within 1 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of L the conference call. The two engaged bolts appear to be fully engaged I
and the upper guide structure is free to move within the vessel.
Engagement of the bolts is based upon torque and a faulty torque
'. reading could have been indicated due to cross-threading, etc. The independent system is supposed to be designed by the NSSS vendor to :
lift the upper guide structure and atta;hed lifting device from its
, current location and. remove it from the. vessel.
i This occurrence will cause a further delay in the outage schedule that
! cannot be estimated until the design of the new support system is known and fabricated. At a minimum it is expected to be 1 1/2 to 2 days. An earlier delay of 4 days was caused by problems associated with l installation of nozzle dams.
ENCLOSURE B NOV 8 1985 N -. . . - . - - . - - - . . . - . - - -.- . - .-. . . - . - - - -
Sequoyah Nuclear Plant, Units 1 and 2 On November 4, 1985, TVA issues a summary of their November 4, 1985 response to the 10 CFR 50.54(f) letter regarding corporate and Sequoyah-rdlated concerns. TVA stated the TVA Board's philosophy and indicated the following actions will be taken to ensure the TVA Board maintains a close awareness of nuclear activities:
- a. the acquisition of a senior nuclear advisor to advise the Board specifically on nuclear matters
- b. the use of frequent special Board briefings dedicated solely to the nuclear program
- c. the assignment of NSRS senior representatives full time to each plant site
- d. the increase of support for the nuclear program by other TVA organizations (General Counsel, Personne, etc.)
- e. the creation of the Office of Inspector General by December 1, 1985
- f. the improvement in compensation to attract and retain experienced personnel In addition, TVA stated that is is establishing a Senior Management Team (hea'ded by H. Parris, Manager of Power and Engineering (Nuclear) to
. establish the duties, responsibilities, and authority for each organization
'in the TVA nuclear program, and listed other corporate goals.
The licensee is comitting to use project managers and program managers to ensure accountability on resolution of key issues and implementation of major efforts. In addition, TVA is settin Tracking System to replace the (at least)seven g up aseparate Corporate Comitment comitment tracking system utilized by different TVA organizations.
With regard to Sequoyah-specific cor.cerns TVA stated their submittal fully describes the EQ program at the facility, with a comitment to verify component location and provide documentation that the equipment is qualified prior to restart.
In response to a concern regarding cable tray support analyses, TVA has performed an evaluation to show that this design program meets all applicable design requirements. In addition, TVA is performing a design control survey for Sequoyah scheduled to be completed in November.
Finally, the licensee stated they are providing information regarding the operational readiness of Sequoyah.
ENCLOSURE B NOV 8 1985
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f Peach Eottom Atomic Power Station, Unit 3 On September 20, 1985, aDailyHighlightwasissuedpertainingtht'he
" identification of cracks" by Philadelphia Electric Company (PECo or the licensee) at Peach Bottom, Unit 3, on the 28-inch recirculation outlet safe end to pipe welds. It was indicated at that time that the safe ends were composed of 316L, low carbon material.
On October 31, 1985, the licensee met with the NRC staff to discuss its findings on these cracks based upon core SAMPLE metallography. The licensee in this presentation concluded that there is no metallographic evidence of IGSCC cracking in the low carbon 316L safe ends and that available evidence indicates that the reported UT indications of cracks are believed to be in result of unique weld root geometry and the presence of small weld defects.
This evidence presented by the licensee is currently under staff review. PECo has indicated that the anormalies presented by this unique weld geometry will be the subject of discussions during a BWR Owner's group meeting scheduled for November 14, 1985.
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ENCLOSURE B NOV S1985 l
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. l NRC TMI PROGRAM OFFICE WEEKLY STATUS REPORT WEEK ENDING NOVEMBER 8, 1985 -
- 1. DEFUELING Six entries were made during the week for movement of fuel debris. The objective was to excavate an area in the debris bed such that the Canister Positioning System (CPS), when loaded with defueling canisters, can rotate without interference. Approximately 2,000 lbs. of debris, consisting mainly of end fittings and attached fuel rods, were moved from the northern quadrants within the reactor vessel to the southern regions.
By the end of the final defueling entry this week, it appeared that the objective had been accomplished. During next week's entry for defueling,
, video inspections will be made to verify the clearance for the CPS. Any remaining partial assemblies or rods that may still be sticking up above the debris bed (308' elevation) will be removed.
The average dose rate to each defueling worker was about 25 to 35 mrem per entry or about 10 mrem per hour. This indicates that fuel movement has not increased the dose rates in areas of the building occupied by defueling workers. Air samples also indicate no significant increase in airborne activity. The NRC is closely monitoring the defueling activities to ensure that operations are conducted safely in accordance with applicable procedures.
._ 2. PLANT STATUS The facility remains in long term cold shutdown with the Reactor Coolant System (RCS) vented to the reactor building atmosphere and the reactor vessel head and plenum assembly removed from the reactor vessel.
The plenum is on its storage stand in the deep end of the fuel
. transfer canal. A dam has been installed between the deep and shallow ends of the fuel transfer canal. The deep end is filled with water to a depth of about 20 feet (about 5 feet above the top of the plenum).
ENCLOSURE B NOV 81985
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- The modified internals indexing fixture is installed on the reactor vessel flange and is flooded to elevation 327 feet 6 inches (15) 4 i
! feet above the top of the core region). The defueling platform is installed over the Internal Indexing Fixture in preparation for j defueling.
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- Calculated reactor decay heat is less than 12 kilowatt's.
- RCS cooling is by natural heat loss to the reactor building ambient atmosphere. Incore thermocouple readings range from 71*F to 95*F l
with an average of 83*F. ,
- The average reactor building temperature is 58 F. The reactor building airborne activity at the Westinghouse platform is 1.8 E-7 3
! 137.
- Spent Fuel Pool "A" is flooded to a depth of 20 feet. About 6 feet l of water is over fuel canister storage racks.
- 3. WASTE MANAGEMENT
! - The Submerged Demineralizer System (SDS) completed processing batch i j 125 Fuel Transfer Canal through Train No.1. A total of 203,369 l gallons was processed in Batch 125. Processing of batch 126
- i. commenced, Fuel Transfer Canal recycle through both Trains and "B" cation sand filter.
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- EPICOR II. is temporarily shutdown while changing out liners.
- - - Total volume processed through SDS to date is 3,174,794 gallons, and
- the total volume processed through EPICOR II is 2,700,737 gallons.
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- 4. DOSE REDUCTION / DECONTAMINATION ACTIVITIES
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" contamination 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 l 305' level of the reactor building.
l - Decontamination of the pressurizer and "A" D-ring is in progress.
f, 5. ENVIRONMENTAL MONITORING i - 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.
consisted of seven daily composite samples taken from October 20 l through October 26, 1985. A gama 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 20 through October 26, 1985. A gamma scan detected no
! reactor related radioactivity.
ENCLOSURE B NOV 8 1985
- _~ - . _ - . - . .. - . . . - . -
3
- The NRC outdoor airborne particulate sampler at the TMI Site collected a sample between October 30 and November 7,1985. 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.
- Defueling Water Cleanup System (DWCS) preoperational testing and modification continued.
- Installation of the vacuum defueling system is in progress.
- Work is in progress on the canister positioning system.
- An integrated test of the canister handling bridges of the Reactor Building and the Fuel Handling Building and the Fuel Transfer Canal is in progress. This will be accomplished by transfer of a canister from the Fuel Transfer Canal to the Spent Fuel Pool through each of the Fuel Transfer Tubes.
- 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 October.
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
~ '
Technical Specification Change Request number 49.
Recovery Operations Plan Change number 31.
- Defueling Safety Evaluation.
SDS Technical Evaluation and System Description Update.
Core Stratification Sample Safety Evaluation.
Heavy Load Handling Safety Evaluation Report.
Defueling Water Cleanup System Technical Evaluation Report, Revision
- 7.
Containment Air Control Envelope Technical Evaluation Report, Revision 5.
- 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 Harrisburg, PA Holiday Inn, 23 South Second Street, Harrisburg, PA, from ,
7:00 PM to approximately 10:00 PM.
ENCLOSURE B NOV 81985
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.
4 l
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i ENCLOSURE B NOV 81985
l OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest -
Week Ending November 8, 1985 Near Term NRC Actions Under the Nuclear Waste Policy Act (NWPA)
Section: 121(a) of NWPA: EPA Final High-Level Waste Standards Status: EPA final rule for Environmental Standards for the Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radio-active Waste will become effective November 16, 1985.
! Action: Staff will review NRC's high-level waste criteria for conformance with EPA standards and will provide a proposed rule to the Commission in December, 1985.
Section: 301 of NWPA. DOE Mission Plan Status: NRC testified on the Mission Plan before the Senate Subcommittee on Nuclear Regulation on October 30, 1985.
NRC testified on November 6, 1985 before the House Subcommittee on Energy Research and Production concerning the implementation of the NWPA, the Mission Plan and the MRS.
.Section: 306 of NWPA: Regulations for Training of Power Plant Personnel
~
Status: The review of the final rulemaking package on Part 55 dealing with simulator training requirements and three associated regulatory guides was completed at the end of October.
Action: The final rulemaking package will undergo Office review through November and is expected to be submitted to ACRS by late November for review.
Section: 141 of NWPA: Licensing of MRS 1
Status: 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.
Action: CRGR is scheduled to be briefed concerning the proposed revisions on November 13, 1985.
ENCLOSURE C 8 B85 2
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) Section: 112(b) of NWPA: Site Nomination and Recommendation Status: 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 i final EAs are now expected by late February, 1986.
DOE's Proposed Rulemaking on the Definition of Byproduct Naterial l On November 1,1985, the Department of Energy (DOE) proposed a rule intended to j clarify the definition of the term " byproduct material" as defined under ;
l Section lle(1) of the Atomic Energy Act. The. proposed interpretive rule is an effort by DOE staff to resolve jurisdictional disputes with EPA over the j regulation of wastes at DOE facilities which contain both radioactive and hazardous constituents (referred to as " mixed" wastes). The stated purpose of t i the proposed rule is to determine DOE's obligations under the Resource Conser-j vation and Recovery Act of 1976 (RCRA), and to determine which of the " mixed" i
wastes produced or owned by DOE should be subject to regulation under that act. While the rule is ostensibly written to specifically resolve only the '
l DOE / EPA mixed waste regulatory questions, it could also impact on NRC licensing activities since it sets out a new approach for determining which substances
{ are to be considered to be byproduct material.
I.
Comments on the proposed rule are due to DOE on December 2, 1985. NRC staff t
i j plan to send comments to DOE and will keep the Commission informed.
t
. n~ sn.nt Fuel Storage i _
As reported previously, during an unlicensed demonstration at the Idaho 1
National Engineering Laboratory (INEL), cracks were observed in non-structural I welds in the fuel basket of the General Nuclear Systems, Inc. (GNSI) CASTOR l
V/21 nodular cast iron dry spent fuel storage cask. On October 31, 1985, a j meeting was held between GNSI and IMSS staff. GNSI examination and analyses
- to date suggest that the cracks were caused by thermal stress due to storing l j fuel with a heat load (about 28.4 kW) beyond the design basis load (21 kW) in I
a basket fabricated with less margin for expansion (i.e., a tighter fit to (
j attain greater thermal efficiency and to permit precise positioning of thermo-l couple leads for the test) than specified in the CASTOR V/21 design submitted j
to NRC. GNSI will submit a preliminary report concerning the INEL occurrence i
in November 1985. NRC staff will examine it and meet again with GNSI.
i Assuming resolution of this matter, GNSI will submit a second and probably j
final report to NRC. At this time it appears the cracks do not compromise the l basket storage capability or safety and that future basket fabrication j tolerances can be assured to eliminate the problem. (
NFS-Erwin i Strike by OCAW members continues. There has been some negotiating between I the Union and NFS within the last four weeks but no resolution has been reached.
j NFS is conducting limited operations of the HEU production, scrap recovery and R&D facilities. No problems with site operations have arisen to date. ENCLOSURE C r
i i i
! NOV 81985 I
OFFICE OF INSPECTION AND ENFORCEMENT Items of Interest Week Ending November 8, 1985
- 1. The following Significant Enforcement Actions were taken during the past week:
- a. EN 85-76, a Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $500 was issued November 7, 1985 to Quality Assurance Testing. This action is based on several violations, including the use of license material by technically unqualified individuals,
- b. EN-85-77, a Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $37,500 was issued November 8,1985 to Commonwealth Edison Company. This action is based on a violation involving the failure to maintain control over the security badge system.
- 2. The following IE Preliminary Notifications were issued during the past week:
- a. PNO-I-85-83, Duquesne Light Company (Beaver Valley Units 1 & 2),
Unmonitored Release from Unit 1 Boric Acid Hold Tank.
- b. PN0-I-85-84, Niagara Mohawk Power Corporation (Nine Mile Point Unit 1),
Unscheduled Outage / Emergency Tech Spec Amendment Needed for Restart.
- c. PNO-I-85-85, Rochester Gas and Electric Corporation (Ginna), Auto-matic Actuation of Cable Tunnel Deluge System.
- d. PNO-I-85-85A, Rochester Gas and Electric Corporation (Ginna), Update on Unusual Event Due to Fire System Actuation,
- e. PNO-II-85-103, U.S. Department of Energy (0ak Ridge, TN), Stolen Radioactive Material Shipping Packages.
- f. PNO-II-85-104,BabcockandWilcoxCompany(LynchburgResearchCenter, Lynchburg, VA), Onsite Flooding.
- g. PNO-II-85-105, Florida Power and Light Company (St. Lucie 1), Core Internals Upper Guide Structure Lifting Rig Failure,
- h. PNO-II-85-106, Mississippi Power and Light Company (Grand Gulf Unit 1), Engineer Injured While Inspecting Cooling Tower.
PNO-II-85-107, Duke Power Compan i.
Shutdown Greater Than 48 Update). Hours (y (0conee Unit 1), Unscheduled J. PNO-III-85-93B, American Electric Power (D.C. Cook), Failure of ReactorTripBreaker(SecondUpdate).
- k. PNO-V-85-75, Sacramento Municipal Utility District (Rancho Seco),
Resumption of Power Operations. ENCLOSURE D NOV 8 1985
i 1
I ;
4
- a. IE Information Notice 85-86, Lightning Strikes at Nuclear Power l
1 Generating Stations was issued November 5,1985 to all nuclear power I reactor facilities holding an operating license or a construction l permit.
i b. Bulletin 85-02, Undervoltage Trip Attachments of Westinghouse DB-50 Type Reactor Trip Breakers, was issued to all Power Reactor Licensees on November 5, 1985. The Bulletin is addressed for action to licensees ,
of operating Westinghouse Power Reactors that have not yet installed i
the automatic shunt trip feature on reactor trip breakers. The basis
- for the Bulletin is the failure of one reactor trip breaker at D. C.
Cook on October 29, followed by testing on November 3 identifying i
degradation of the breaker that functioned correctly on October 29.
f 4. Other Items 1
i b. Resident Inspector Seminar -
l !
{
Director, IE met with principal staff in Region III November 5, 1985 to address the Resident Inspector Seminar.
,b. ACRS Brief l
f Representatives of the Division of Emergency Preparedness and ,
2 Engineering Response and NRR briefied the ACRS regarding Recent j~ Significant Operating Events at Nuclear Power Plants on November 7, 1985.
I j c. Maintenance Training Overview class A representative of Operating Reactor Programs Branch, Division of j Inspection Programs, attended a training class, " Maintenance Training 5 i Overview." at the GE BWR Services Training Facility in San Jose, i
CA, November 4-8, 1985.
1 i d. NFS License Renewal A representative of Special Materials Programs Branch, Division of Inspection Programs, participated in a meeting November 6, 1985 j
in Atlanta with.the Region II staff and NMSS to discuss the license renewal for the NFS facility.
i ENCLOSURE D ;
NOV 8 1985
- e. Hatch 1 Drywell Inerting and Purge Line Crack Representatives of Events Analysis Branch, Division of' Emergency Preparedness and Engineering Response were in Region II on November 8, 1985 to participate in a meeting with Georgia Power /GE to discuss the Hatch I drywell inerting and purge line crack of December 1984.
- f. Fort Calhoun Installation Inspection Representatives of Operating Reactor Programs Branch, Division of Inspection, and consultants were at the Fort Calhoun site November 4,
- 1985 to begin the installation inspection part of the trial outage inspection program.
- g. Comanche Peak Inspection Representatives of Reactor Construction Programs Branch, Division of Inspection were at Comanche Peak November 4, 1985 to discuss and observe Comanche Peak Response Team inspection activities.
- h. Incident Response Program Chief, Incident Response, Division of Emergency Preparedness and Engineering Response, held a briefing on November 6, 1985 for Public Affairs Officers on the agency's incident response program.
- i. Reentry-Recovery Issues Conference
~
Director, and representatives of Division of Emergency Preapredness and Engineering Response attended a Reentry-Recovery Issues Con-ference November 7-8, 1985, which was a preparatory meeting for the Relocation Tabletop Exercise to be held in December. The Region !
Administrator and staff also attended.
J. Systematic Assessment of Licensee Performance (SALP) Manual Chapter Revision A revision to the SALP Manual Chapter was forwarded to the regional offices on November 5, 1985 for implementation. One important change is formal inclusion of Training and Qualification Effectiveness as a separate SALP functional area.
- k. Inspection Program Revision The Division of Inspection Programs issued on November 5, 1985 a revision to the Operating Reactor Inspection Program which provided guidance for allocating inspection resources and for development of site-specific inspection plans. A major purpose of the revision is to establish an approach for focusing inspection attention on poor licensee performance areas.
N OWRE D NOV 8 1985
e
- 1. Special Safety System Functional Inspection ,
A special safety system functional inspection is in prog'ress at l
Pilgrim with onsite inspection activities scheduled to be completed on November 22, 1985. Particular attention is directed to the details of modifications and design control, quality of maintenance and surveillance, and adequacy of testing applicable to the selected i safety system. The first inspection of this type was conducted i
at Turkey Point in August / September.
i
- m. Design Assurance Program
! A representative of Division of Quality Assurance, Vendor, and Technical Training Center participated this week in the public J meeting on Comanche Peak to make a presentation on the status of the IE overview of the applicant's Design Assurance Program.
J
- n. Vendor Inspections
! The following inspections were conducted this week:
4 (1) Limotorque, Lynchburg, VA - to review vendor design control j
i activities and related concerns associated with PORV, valve /
actuators, and magnesium rotors used in Reliance motors.
l f
(2) Illinois Fabricators, Bradley, ILL - allegation inspection.
~ '
(3) Arkansas Nuclear One, Russellville, AK - to assist NRR in their
~
survey of maintenance and surveillance at Arkansas Nuclear One i
i Unit 2.
4
- o. Civil Penalties Paid (1) On November 1, 1985, payment in the amount of $2,000 was received from Princeton University (Princeton, NJ) for enforcement action (EA 85-70) relating to health physics ;
violations.
(2) On November 8, 1985, payment in the amount of $50,000 was received from Arizona Public Service Company (Palo Verde) for enforcement action (EA 85-87) relating to violations involving the inoperability of the containment atmosphere portion of the PASS.
i ENCLOSURE D NOV 8 1985
i 0FFICE OF NUCLEAR REGULATORY RESEARCH 4
Items of Interest 1
Week Ending November 8,1985 2D/3D Full-scale testing of emergency core cooling (ECC) perfomance is conducted in the international 20/3D facilities Upper Plenum Test .
Facility (UPTF) and the Slab Core Test Facility (SCTF). Data is provided i on fluid-fluid mixing (pressurized themal shock) PTS related, ECC bypass, upper-plenum deentrainment, and fallback and condensation effects.
The 2D/3D Program participants met in Bethesda, Maryland on ,
4 October 28-31, 1985 to discuss the. status of the program in each country '
, and to resolve any outstanding issues. Also present at the meeting were 1 personnel from NRR and the pressurized water reactor vendors (Westinghouse Electric Corporation, Combustion Engineering Incorporated, and Babcock and Wilcox Company).
The Japan Atomic Energy Research Institute reported that the test results .
from its Slab Core Test Facility, which simulates a radial segment of a !
PWR core, show that the simulated core with 2000 electrically heated rods was effectively cooled by the steam and water mixtures and quenched within 5 minutes. The quench pattern was nearly uniform (within 10 percent
, deviation) in the radial direction although the power level was different J . ,by as much as 40 percent; the high power zone being 20 percent higher than
! the average and tie low power zone 20 percent lower. There seem to be
] _ significant flows in the horizontal direction, effectively mitigating the power level differences in the radial direction. It appears that the high power zone gets more emergency core cooling (ECC) flows for the following two reasons: (1) generation of more steam, thus inducing a higher buoyancy force, and (2) accumulation of less liquid above the upper tie-plate, thus providing a path of less resistance for ECC flows from the lower plenum to the upper plenur'.
The heat transfer in the high power zone improves so much that the quench front in the higher power zone actually moves faster than the low power zone, although the difference is not significant (less than 10 percent).
i i
ENCLOSURE E NOV 81985
- i
! [,
) .
l Semiscale .
i semiscale Test S-NH-1 was successfully completed this week. Test S-NH-1 i
- simulates a 0.5 percent cold-leg break (2 inch diameter) in a 4-loop. 3411 MW(t) connercial reactor in which the high pressure injection emergency 1 l core cooling system is inoperative. This break scenario in a connercial !
4 reactor has the potential for core dryout and heatup while still at high ;
f primary coolant pressures, which precludes accumulator injection. Thus it ;
j is necessary for operators to take timely and appropriate actions to ,
i reduce the primary coolant system pressure such that the accumulators and l low pressure injection system (LPIS) can operate, assuring long-term !
, core cooling before core degradation occurs. In this test, recovery ,
1 operations were initiated when peak cladding temperature reached 1000*F. !
At that time the operators latched open the steam generator atmospheric !
dump valves, enabling the primary coolant system to depressurize as a !
' result of the improved heat transfer to the secondary coolant system !
- through an operation normally referenced to as feed and steam cooldown. '
This process was continued until the LPIS set point of 198 psia was
)
reached. '
i !
l
{ International Code Assessment and Applications Program (ICAP) l ' A meeting of the participants in ICAP was held on October 21, 1985.
1 Representatives from Austria, Belgium, Finland. France. Federal Republic of Germany. Italy, Netherlands, Spain, Sweden. Switzerland, United .
4 Kingdom, and the Joint Research Center Ispra Establishment attended, as .
well as the NRC and its contractors.
! The program is concerned with the assessment, application, and improvement of the codes TRAC-PWR, RELAP5, and TRAC-BWR. The assessment effort includes separate effects and integral experiments, and applications of '
the codes to power plant transients. The formation of an international L cooperative program was undertaken to utilize the considerable experience l being gained through use of the codes in different countries. The program
} was organized during 1984-1985 through bilateral agreements between the i NRC and the nuclear safety authorities of the different countries. An 1
information meeting was hosted by the NRC in April 1985. The current
, meeting was aimed at the establishment of a Program Group, the finalization of principles by which the program will be managed, and the l discussion of work plans for 1986. '
i t
Countries have begun generating information using the codes and providing results to the NRC. Quarterly newsletters prepared by the Los Alamos National Laboratory on TRAC-PWR and by the Idaho National Ingineering
- Laboratory on RELAP5 and TRAC-BWR provide regular summaries of status and progress. The first ICAP specialist meeting is planned for the May-June 1986 time frame, ,
i
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ENCLOSURE E l NOV 8 1985
{
. . _ . - - _ _ _ _ . - _ - , . - - . _ _ . - - _ . . , _ - - ~ _ _ . _ _ , _ _ - - . - - . _ . - , . _ _ . _ - - _ , . . .
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Degraded Core Coolability Experiment DCC-3 in ACRR f
4 i The last of three experiments on Degraded Core Coolability, experiment ,
! DCC-3, was performed successfully in the ACRR test reactor at Sandia :
l National Laboratory. In the DCC experiments the limiting conditions !
j were measured for which coolability can be restored and maintained by t
reflooding a severely damaged reactor core, as in the TMI-2 accident.
! The primary purpose of these experiments was to validate for LWR-i specific accident conditions the relatively advanced core-debris t
! coolability models that have been developed in LMFBR safety research.
j The LWR-specific conditions of importance are the pressure range up to 17.MPa (2,500 psi) for the water coolant, deep debris beds, l i
1 variable inlet flow down to zero, and LWR specific debris charac- l I teristics. Experiment DCC-3 was entirely funded by NRC's foreign ,
program partners in the joint international Severe Fuel Damage and j j
j Source Term Research Program. ;
In the DCC experiments, a particulate bed with the desired particle-
, size distribution is constructed from crushed and sieved reactor
! fuel (U0 ) in a water-filled experiment capsule, and is then internally ,
I fission $eated in the ACRR experiment cavity in simulation of the !
l internal fission-product-decay heating of water-cooled core debris in
! a reactor accident. An array of 34 thermocouples throughout the bed
{
detects the local dry-out coolability limit of the bed for a specific
! set of conditions by the ramp increase in the temperature of one or ;
more of the bed thermocouples above saturation that follows dry out. ;
Experiments DCC-1 and DCC-2, respectively, used a relatively fine :
j
~
' and a relatively coarse particle size distribution in the bed and j covered the full range of pressu"e. Experiment DCC-3 used a bed .
vertically stratified by particle size with the fine debris at the i
l '
. top, a' configuration that occurs naturally from debris settling through water. Analysis and previous experiments have shown that ;
this geometry can reduce the dry out coolability limit by as much
) as an order of magnitude under conditions of no inlet flow because l
of capillary pressure (the liquid is sucked towards the fine debris, i
- reducing internal water flow to the bottom of the bed). DCC-3 also
! had capability for measuring the effect of inlet flow on the dry-out i coolability limit. l 1 '
I The DCC-3 experiment was performed successfully with a 10-day run in ACRR. Fifty bed dryouts were measured that covered the planned j j
flowandno-flowparameterrangeupto7.0MPa(1,000 psi). Beyond l dryout behavior (bed thermal characteristics) was also measured up i
to 1300K. Preliminary results appear to be in agreement with .
l the accepted theoretical model (Lipinski one-dimensional model), with I the strong vertical stratification of the bed reducing the bed specific I
) power required for dry out by about an order of magnitude from that i for an unstratified bed. This large reduction, however, was eliminated by relatively small inlet flow from the bottom of the bed, as predicted, and the effect of inlet flow in general in increasing the specific
- power required to dry-out the bed was in agreement with the ENCLOSURE E i t 8 Mgoretical model. *
(
NOV l . _ _ . . _ _ . _ _ . _____
. i Remotec Survey Robot (SURBOT) Scheduled For Demonstration at NRC In 1984, the Office of Nuclear Regulatory Research, under the S' mall Business Innovative Research Act, funded a robotics demonstration project with Remote Technology Corporation, Oak Ridge, Tennessee. Phase I of the contract resulted in a determination that the use of remotely controlled survey and inspection devices was feasible for cost effective applications in certain high dose areas of nuclear power plants.
Phase II has resulted in the fabrication (from commercially available components) of a tethered survey and inspection system (SURBOT) scheduled to be demonstrated in an operating power plant in FY 86. The Remotec robot is capable of: taking radiation measurements; air sampling; surface contamination sampling; temperature, humidity and sound measurements; and high-resolution viewing of critical components. In addition the system can be programed to perform a variety of tasks without operator intervention. The system has just completed extensive testing by the Electric Power Research Institute (EPRI) which was enthusiastic about its performance.
SURBOT will be demonstrated continuously for the hRC staff and others on Wednesday, December 11, 1985, in Room 118 of the Phillips Building from 12:00p.m. to 4:30p.m. This will be an informal program and attendance for any half-hour during the afternoon should be adaquate to see the range of capabilities of SURBOT. Attendees will have an opportunity to operate the system.
~
International Workshops on Dosimetry of Beta Particles and Low-Energy X-Rays and Radiation Damage to Skin Two workshops, co-sponsored by the U.S. Department of Energy and EURADOS, the European Radiation Dosimetry Group, were held recently at the Commissariat a l'Energie Atomic (CEA) in Saclay, France. The first workshop. Dosimetry of Beta Particles and Low-Energy X-rays, was held October 7-9, 1985; the second, Radiation Damage to Skin, Fundamental and Practical Aspects, was held October 9-11, 1985. Several important conclusions that could affect radiation protection in the U.S.A. were reached by the participants. They reaffirmed that the dose from low-energy x-rays and from beta particles should continue to be measured at a depth in tissue of 70 um as recomended by the International Commission on Radiation Protection (ICRP-26) and as required by current NRC regulations. Commercially-available personnel dosimeters are not suitable for direct dose measurement at a tissue depth of 70 um, but the dose at this depth can be estimated by extrapolation if a multi-element dosimeter is used. Since i
i ENCLOSURE E i NOV 8 1995
many commonly-used dosimeters do not use enough elements for this extrapolation, estimates at greater depths are usually accepted. Another consensus of the group was that ultra-thin thermoluminescent dosimeters, when fully adaptable for use in the workplace, will replace the multi-element dosimeters now commonly used for personnel dosimetry of beta particles and
- low-energy x-rays. From other information presented it appears that the minimum dose measurable using thermoluminescent dosimeters may be lowered
! considerably by using computer analysis techniques with current dosimeter readout equipment. The workshop participants exhibited special interest in a portable beta spectrometer whose performance is currently being evaluated in field tests conducted for the NRC by the Idaho National Engineering Laboratory.
r
Contact:
R. B. Neel 42-74559 i
r G S
)
ENCLOSURE E i
NOV S 1985
' l l
l RES Rulemaking Activities l Severe Accident Risk Assessment l
There are several important highlights from last week's activities, sumarized below:
- 1. Overall responsibility for the Zion analysis was assigned to BNL, with SNL providing an accident sequence analysis in a letter report and BCL providing source tenn code runs,
- 2. Agreement was reached by all parties on the approach to sensitivity analyses, and a final letter cf instruction will be sent to SNL within a week.
- 3. Schedules for all plants were completely reviewed and revised and presented in the November 4 Consnission briefing (ref. Attachment)
While slips of about one to two months have been typical, these were expected due to the very optimistic nature of original schedule. The schedule for the public draft of NUREG-1150 is unchanged --mid sumer of 1986, 4 A kickoff meeting on uncertainty white papers will be held with all project managers on November 7. This work will be closely coordinated with SNL and BNL so as to result in comon assumptions and ranges of parameters to the extent possible in NUREG-1150. The
,' work will follow the guidelines established in 2, above.
Shipping Cask Response to Severe Transportation Accidents-Modal Study The purpose of this study is to determine the degree of safety being provided during shipments of spent fuel. This purpose is being ;
accomplished by assessing the performance of licensed casks when subjected ;
to severe transportation accident environments. A final report is !
scheduled to be completed by mid-December.
In a discussion with F. Gillespie, G. Cumings (LLNL) indicated that LLNL is adhering to the schedule for submission of specific sections of the Engineering Document and supporting Appendix material. The introductory section and the outline for the analysis and results sections were received November 4. Dir RES and D Dir NMSS will be visiting LLNL on November 14 for an overall program review and to review progress on i the final report documentation.
Cost Benefit Workshops Past Comission and EDO policy and planning guidance suggest "... existing guidance on performing cost-benefit analysis should be further ,
developed." In accordance with this guidance, RES under a technical assistance contract with PNL has completed a series of cost-benefit ENCLOSURE E workshops at all the Regions to support current policies and procedures affecting management of plant-specific backfitting of nuclear power plants. !
NOV 8 1985 .
t
4 i L
- 7-i I The workshop had two objectives:
(1) to identify recognized l
guidance documents within the NRC to support perform l
and (2) to train the staff in the application of existing cost-benefit methods to backfits including resources available to assist in performing high quality regulatory analyses.
The workshops began in late July 1985 and ended November 4, 1985.
i l
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ENCLOSURE E
}
j NOV 81985
g 10/31/85 i *
< (EVISED)
FINAL SARRP SCHEDULE FOR NUREG-1150 AND NRR SUPPORT ,.
5
- SEQUOYAH GRAND GULF ZION
- 1.A5ALLE ACTIVITY SURRY PEACH BOTTOM
- 1. ACCIDENT SEQUENCE C C C C 12/19 ,
INITIAL INPUT C -
- 2. SOURCE TERM C C C C C 1/23 BINNING
- 3. NUMBER OF SOURCE
~8 3 N6 N6 TERM CODE RUNS ~3 6 C C 11/15 11/15 12/31 3/20/86
- 4. SOURCE TERM CODE RUNS (EXCEPT 1)
C C 11/22 11/25 1/15/86 4/14/86
- 5. RELEASE CHARACTER-ISTICS (EXCEPT 1)
C 11/15 12/10 12/11 1/31/86 4/28/86 '
D. CONSEQUENCE CALC.
(EXCEPT 1)
- 7. REFINE ACCIDENT C 11/11 11/15 12/13 N/A . 2/27/86 '
SEQUENCES
- 8. CONTAINENT TREES 11/15 12/9 12/3 1/20/86 1/31/86 5/28/86-DRAFT REPORT
- 9. BASELINE RISK 11/25 12/18 1/7/86 2/15/86 5/26/86 CALCULATION 11/19
- 10. RISK / RISK RED. 1/21/86 3/14/86 " 3/28/86 " 6/9/86*'!
TABLES . 12/9 1/20/86 :
- 11. RISK / RISK RED. DRAFT 4/1/86 " 4/15/86 4/30/86 7/7/86 DETAILED RPT. 2/26/86 " 4/6/86 "
- 12. RISK / RISK RED FINAL 9/1/86 m
DETAILED RPT. 4/23/86 6/1/86 5/27/86 6/10/86 6/30/86 M
hoTENTATIVESCHEDULE A
m
- INCLUDES FINAL SENSITIVITY ANALYSES AND UNCERTAINTY RANGES ATTACHMENT TO RES RUI.El'AKING ACTIVITIES
i
.a.
Publications to be Issued in the Near Future
Title:
Instrument Setpoints for Safety-Related Systems (R. G.1.105, Rev. 2)
Description:
This guide describes a method acceptable to the NRC staff for complying with the Commission's regulations for ensuring that instrument setpoints are initially within and remain within the technical specification limits.
Contact:
A. S. Hintze 443-7712
Title:
Radiation Damage to Reactor Vessel Materials (Draft R. G.1.99, Proposed Rev. 2)
Description:
Provides calculative procedures and other guidance for 4
accounting for radiation damage in regulating fracture prevention of reactor vessels.
Contact:
Pryor N. Randall 443-7711 or 492-8186 e e O
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EflCLOSURE E NOV 8 BB5
ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING NOVEMBER 8, 1985 International Visitors On Monday and Tuesday Mr. Michel Laverie, Deputy Chief of the French Service Central de Surete des Installations Nucleaires (SC.,1N),
accompanied by three SCSIN members, met with NRR, RES, NMSS and IP staff for technical discussions. Technical topics covered included steam generator tubes, station blackout and decommissioning.
On Monday and Tuesday Mr. B. John Darlaston of the UK Central Electricity Generating Board's Berkeley Nuclear Laboratories met representatives of the NRR Divisions of Engineering and Systems Integration and the RES Divisions of Engineering Technology and Risk Analysis and Operations to discuss various issues related to material and system integrity.
On Tuesday Messrs. Ishibashi and Takahashi, lawyers of the Comittee of Environmental Pollution Prevention of Japan's Federation of Bar Associations, visited NRC. The visitors are studying the potential health hazards of the proposed Japanese reprocessing and waste storage facility in the Aomori Prefecture. They met with ELD, RES and NMSS to gather information on U.S. experience and plans regarding nuclear waste
, management and reprocessing.
On Thursday Messrs A. Pugliesi, T. Sano, and L. Lojello of Italy's ENEA/ DISP visited NRR to discuss recent developments in geotechnology
- and site specific seismicity.
On Friday a five-member technical team from China's Ministry of Nuclear Energy, Radiometrology Center, met with staff members from NMSS, RES, and IP for a discussion of NRC's regulations and radiometrology. The purpose of the team's visit to the U.S., which is being hosted by the National Bureau of Standards, is to learn about the present status and future development of research work in the U.S., with emphasis on neutron standards, radionuclides standardization, and radiation dosimetry standards.
Foreign Trip Reports Guy H. Cunningham III, Executive Legal Director September 29-October 2, 1985; Visited the FRG:
Mr. Cunningham attended the International Nuclear Law Association Congress, Nuclear Inter-Jura 1985, in Constance. As Chainnan of the Association's working group on nuclear third party liability issues, he presented the report of the working group's activities of the past two years.
ENCLOSURE G NOV 8 1935
l 2
- Foreign Trip Reports continued .
. Shlomo S. Yaniv, HEBR/RES September 30-October 2, 1985; Visited the FRG:
Mr. Yaniv attended the Workshop on Radiological Health Effects Models for Nuclear Accident Consequence Anflysis at the Karlsruhe Nuclear Research Center. Its objective was the evaluation of the health effects models and risk coefficients propoied.in NUREG/CR-4214, published by ,
Sandia National Laboratory, under cdatract tt) NRC.
Themis P. Speis. Director, DST /NRR (Head of NRC Delegatinn)
September 30-October 4, 1985; Visited FrancL:
The purpose of the delegation's trip was to discuss NRC's initial draft report on the design differences between the French P4 1300 MWe plant and a typical U.S. four-loop PWR. The participants visited the Paluel nuclear power plant on October 1, 4
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ENCLOSURE G
_NOV 8 1985 ,
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OFFICE OF STATE PROGRAMS ITEMS OF INTEREST WEEK ENDING NOVEMBER 8, 1985 MAINE INITIATIVE ON LOW-LEVEL WASTE According to United Press International reports, Maine voters approved en initiative which would allow them the right to vote for or against any plan for the storage or disposal of Low-Level Waste in the State. UPI claims that to avoid a run-off, the vote must be at least 50%. The measure in this instance reportedly won by 50.2%. These figures are based solely on UPI reports (the only ones available at this time), and as such are unofficial.
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ENCLOSURE H NOV 81B85 e e +- -m e .y % .* w---- ,&y -
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OFFICE OF RESOURCE MANAGEMENT
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' Item Of Interest ,
Week Ending November 8, 1985 Energy and Water Development Appropriations Act ThePresidentsignedtheEnergyandWaterDevelopmentAppropriationsActof FY 1986 (Public Law 99-141) on November 1, 1985. This Act appropriates
$418 million to NRC for FY 1986.
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I ENCLOSURE I
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' NOV 81985
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REGION I ENCLOSURE TMI-1 STATUS REPORT FOR THE PERIOD NOVEMBER l-8, 1985
- 1. Plant Status As of 8:00 a.m. cn November 8, 1985, TMI-1 was at 48% power.
- 2. Test Program Status The licensee's planned test program and current status for restart of TMI-1 are shown on the attached Figure 1. - Special testing planned for the afternoon on November 8,1985 includes an integrated control system (ICS) tuning test that requires a change in power from 48% to 40%, then back to 48%. This test was originally planned for the week of October 27, 1985, but was rescheduled, pending completion of ICS system troubleshooting and maintenance on a feedwater pump controller to permit the test to be performed with both of the main feedwater pumps in automatic.
- 3. Facility Operations Summary Steady-state operation at 48% power continued throughout the period.
- 4. Items of Special Interest
' NRC Notifications As has been the case in prior periods, there were no events that required
- notification of NRC by the licensee. There were, however, several events of interest and they are discussed below.
Moisture Separator Drain System Steam Leak On Saturday, November 2, 1985, at 9:30 a.m., the licensee attempted to repair a small water leak on a flange in the secondary plant moisture separator drain system which is located in the turbine building. Because the section of piping was not effectively isolated, a steam leak occurred at the flange as the flange bolts were loosened. The leak was fed by relatively hot water from the steam and feedwater system. Some of the workers involved in the repair received superficial burns that did not require offsite medical attention. The steam leak lasted approximately 20 minutes. Although a minor perturbation was noticed in feedwater flow, the plant remained at steady-state 48% power conditions. This matter is reported for information and is not a significant NRC concern.
Loss of Alternate Power Source for ICS/NNI Bus On November 5,1985, a 120 volt alternating current bus was deenergized by licensee technicians who opened a supply breaker in response to arcing ENCLOSURE L NOV 81985
e 2
k and sparking at an adjacent breaker. The technicians.were performing i breaker preventive maintenance on an engineered safeguards bus at the I time. Although no significant loads were lost by the bus being deener-I- gized, the electrical incident was apparently due to technician error and
- is of interest because it had the potential for causing a plant transient.
1 J The deenergized bus was an alternate power source for the integrated control system (ICS)/non-nuclear instrumentation (NNI) bus. The ICS and NNI remained energized. The reactor protection and engineered safeguard l-actuation systems were unaffected because they were powered from separate vital buses. The licensee has taken disciplinary action against the technicians. Additional licensee corrective action will be reviewed by j the TMI-1 Restart Staff.
! Letdown Cooler Leakage 1
On November 5, 1985, the licensee removed one of the two letdown coolers from service because of an indicated leakage at the rate of 1.3 liters / day.
f-
- The letdown cooler is part of the makeup and purification system and is .
used to lower the temperature of the reactor coolant such that it can be processed and then returned to the' reactor coolant system. Leakage of j the reactor coolant was into the intermediate closed cycle cooling water system, a non-safety system. The leakage was first detected on October ,
- 24, 1985, by radioactive noble gas sampling and trended on a daily basis.
Although the cooler is still considered to be operable by the licensee, l
, it is not in service. The licensee has two spare letdown coolers available
- onsite if needed. This matter is an item of interest to the TMI-1 Restart
. , St&ff because of the leakage of reactor coolant..
- Emergency Drill i The licensee is planning a practice emergency drill on November 13, 1985, I in preparation for the annual emergency exercise on November 20, 1985.
The drill was originally scheduled for November 6, 1985. The TMI-1 Restart Staff, in conjunction with NRC TMI-2 Program Office personnel,
! plans to participate in the practice drill for a limited time to exercise
! the NRC site emergency plan.
- 5. NRC Thermoluminescent Dosimeter (TLD) Special Monitoring Program for TMI l The special NRC TLDs for TMI for the period October 18 - October 31,.
1985, were processed at the Region I TLD laboratory. The TLD readings are provided in the attached Table A.' The monitoring results indicate i
i that the radiation levels at these monitoring locations remain at natural
- background levels. These readings can be expected to vary slightly~from j period to period due to variations in natural background, independent of
. releases from the plants.
i ENCLOSWE L )
NOV 8 1985 l '
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- 6. Meeting with Members of TMI Alert On November 11, 1985, the TMI-1 Restart Staff Director and Restart Manager met with three members of TMI Alert (TMIA). The primary purpose of the meeting was to discuss the usefulness of the TMI-1 Restart Staff's weekly status reports Nom TMI Alert's perspective. Their general con-clusions were that the reports were of little value in that they contained insufficient detail and were received too late. WeWe informed them that also discussed andwe
' were attempting to improve both of these areas.
answered questions regarding recent activities at TMI-1 addressed in the weekly status reports. Some of the requests for more technical information could not be addressed at the meeting and will be provided in a letter.
The role of TMIA also was discussed. During our conversation TMIA representatives indicated that they now perform a connunityTheir service by responding to questions and concerns by the local public.
independent review of GPUN local environmental (background) radiation data is available through the local emergency management agency office.
The TMIA representatives expressed their view that they represent the majority of local opinion which they believe was reflected in the local referendum (against the restart of TMI-1) a number of years ago. They expressed their dismay that federal agencies (primarily NRC) repeatedly have ruled in favor of the licensee ever since the first significant decision since the TMI-2 accident -- the venting of krypton from the TMI-2 reactor building. Consequently, they continue to believe these same
- federal agencies are not really concerned with local public health and
- , safety.
- 7. TMI-1 Restart Staff Status During the Period The TMI-1 Restart Staff continued 16-hour shift coverage during the period. The shifts were manned by NRC personnel from Region II and the Reactor Training Center, and by a reactor operator examiner from EG&G Idaho, Inc., an NRC contractor. Two Region I reactor engineers and a senior radiation specialist were onsite during portions of the period to augment the resident inspection staff.
The staff's inspection plan for this period covered the primary functional areas of operations, maintenance, surveillance, and radiation protection with the division of responsibility as noted in previous status reports.
The TMI-1 Restart Staff continued to evaluate the performance of licensee personnel and the plant to determine whether the licensee should be permit-1 ted to proceed beyond the next hold point, which is reached after 30 days of operation at 48% power.
Contact from the public was minimal throughout the period. We continued to maintain daily contact with representatives of the Connonwealth of Pennsylvania during this period.
ENCLOSURE L NOV 8 1985
4 The TMI-1 Restart Staff issued two daily highlight reports for the Executive Director for Operations on November 4 and 6,1985, regarding the moisture separator drain system leak, the 120V ac bus deenergization, and the letdown cooler leakage. The fourth weekly status report for the period October 25-November 1, 1985, was issued on November 1, 1985.
Inspection Report No. 50-289/85-24, for the period October 11-18, 1985, was issued on November 7, 1985. The findings were generally favorable, however, we noted an adverse trend in the supervisory oversight of person-nel working in safety-related creas. This has resulted in instances of personnel standing on safety equipment and a potential violation regarding scaffolding that was not properly secured. We noted that although no adverse effect on the plant has yet resulted, the licensee's prompt attention is needed to reverse this trend.
- 8. TMI-1 Restart Staff Composition During Period The TMI-1 Restart Staff was comprised of the following personnel during the period:
W. F. Kane, TMI-1 Restart Director R. J. Conte, TMI-1 Restart Manager D. R. Haverkamp, Technical Assistant F. I. Young, Resident Inspector, TMI-1 D. M. Johnson, Reactor Engineer R. J. Urban, Reactor Engineer J. R. White, Senior Radiation Specialist T. L. Morgan, Shift Inspector, EG&G Idaho, Inc.
- - L. J. Reidinger, Shift Inspector, Reactor Training Center T. F. Stetka, Shift Inspector, Region II C. P. Hix, Secretary L. M. Prough, Secretary ENCLOSURE L NOV 81985
TABLE A TMI SPECIAL TLD MONITORING RESULTS Station Distance Direction Baseline Field Exposure 10/18/85-10/31/85 mR mR/ day (miles) (Meanfdays.d.) (Mean , s.d.; total uncertainty)
Control - 0.17 + 0.0007; 0.03 2 3.9 101 0.19 + 0.02 0.20 T 0.01; 0.03 3 2.7 109 0.16 7 0.02 0.16 T 0.01; 0.02 4 1.8 163 0.16 7 0.02 0.18 T 0.01; 0.03 5 2.2 161 0.18 T 0.02 0.16 T 0.003; 0.02 6 1.0 150 0.17 7 0.03 0.18 I 0.005; 0.03 7 0.6 136 0.17 7 0.02 0.16 T 0.001; 0.02 8 0.4 83 0.16 T 0.03 0.17 7 0.02; 0.03 9 0.5 60 0.16 T 0.02 0.18 I 0.001; 0.03 10 1.7 1 0.14 T 0.02 TLD MTSSING 11 0.9 25 0.16 T 0.01 0.17 + 0.003; 0.03 12 2.8 46 0.16 T 0.02 0.18 T 0.004; 0.03 14 2.5 358 0.14 T 0.02 0.18 T 0.01 0.03 16 3.1 0 0.14 T 0.02 0.17 7 0.004; 0.03 18 3.5 349 0.17 7 0.03 0.15 T 0.01; 0.02 19 3.2 343 0.17 T 0.02 0.19 I 0.004; 0.03 20 5.0 318 0.16 7 0.01 0.16 T 0.004; 0.02 21 1.3 348 0.13 T 0.01 0.15 7 0.01; 0.02 22 3.1 17 0.17 7 0.02 0.18 T 0.03; 0.03 23 3.8 64 0.13 T 0.01 0.17 7 0.01; 0.03 24 3.6 44 0.17 7 0.01 0.17 7 0.01; 0.03
- , Control ! 0.14 T 0.001; 0.02 34 2.3 267 0.17 + 0.01 0.18 I 0.02; 0.03 35 1.8 299 0.17 T 0.01 TLD MTSSING 36 1.2 267 0.12 T 0.02 0.16 + 0.02; 0.02 37 1.4 256 0.14 T 0.01 0.16 T 0.01;'O.02 38 1.9 225 0.18 T 0.02 0.17 I 0.003; 0.03 39 2.1 200 0.13 T 0.01 0.16 I 0.01; 0.02 40 2.5 204 0.16 T 0.02 0.17 7 0.01; 0.03 46 3.0 177 0.14 T 0.02 0.17 7 0.001; 0.03 50 4.9 145 0.1410.04 0.1610.001;0.02 Abbreviations:
mR = millirem s.d. = standard deviation REMARKS:
Twenty-nine environmental (offsite) locations are monitored on a two-week exchange cycle using special TLDs for the TMI site. Two control TLDs were stored in a 1/2" thick lead shield at the NRC TMI Office for two weeks. The baseline data for the environmental monitoring were calculated using the past ten quarters of monitoring results. To date, all monitoring results indicate normal natural background radiation levels.
ENCLOSURE L NOV 8 1985
REGION III STATUS REPORT DAVIS-BESSE LOSS OF FEEDWATER EVENT -
NOVEMBER 8, 1985 ,
Plant Status The plant remains in cold shutdown. The circulating water canal is drained.
Decay heat removal loop No.1 is filled and being tested in preparation for taking decay heat loop No. 2 out of service for maintenance. Emergency Diesel Generator (EDG) No.1 is now operable. Both EDGs have a control system design deficiency that renders them inoperable throughout the ten minute period that they run at idle speed following normal shutdown. While running at idle speed the output circuit breaker will open after closing due to an undervoltage condition on the associated bus. The licensee has taken appropriate actions to compensate for and correct this condition, which was discovered during the licensee's review of IE Notice 85-73. The diesel firewater pump is now operable.
ENCLOSURE L l
NOV 8 1985 i
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Region III STAFF ACTIONS AS ASSIGNED BY W. DIRCKS MEMO OF AUGUST 5, 1985
- 1. Item: Adequacy of the licensee's management' and maintenance activities m
03 ACTION STATUS / COMMENTS (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 confirmed previous concerns identified programs and post-trip reviews). by Region III. A followup team inspection is planned for early 1986. 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 / COMMENTS (a) Monitor the licensee's trouble- Troubleshooting activities related to containment isolation shooting activities valves AF599 and Ar608 are complete. Region III specialists are evaluating and monitoring MOVATS testing on other safety-related motor operated valves. About 75% of 166 valves have been completed.
(e) Determine that the procedures for Limitorque 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 Confirmatory testing will be performed during startup.
switches are clear and proper, and that associated training programs are adequate. Confirm that adjustment settings are consistent with plant procedures.
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h 7. Item: Adequacy of emergency notifications STATUS /C0pmENTS m ACTION ,
in Investigation of the adequacy of the licensee's procedures S (a) Verify the adequacy of the licensee's and training for the reporting of events to the NRC procedures and training for the report-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.
- 8. Item: Reliability of AFW pump turbines STATUS / COMMENTS ACTION Troubleshooting activities are complete. Regior. III (a) Monitor the licensee's trouble- will monitor confirmatory testing during plant startup shooting activities including possible hot plant operation to as part of startup test activities.
confirm failure mode.
Results of test review group meetings have culminated (d) Verify that the AFW system has been in the development of a charter outlining test review group adequately tested to confir1n system 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.
- 9. Item: Reliability of the PORV ACTION STATUS / COMMENTS Troubleshonting activities have been comple'ed.
t Confirmatory (a) Monitor the licensee's trouble- testing will be conducted at operating temperature and shooting activities pressure. Testing of an equivalent valve indicated a lower m
z flow condition than expected. Flow results from Crosby (valve manufacturer) testing were higher than the flow results from g the Marshall Steam Station test facility. All test data indi-g cated flow was less than expected. The licensee will continue g to evaluate this information.
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- Resolution of equipment deficiencies t ca '
ACTION .
STATUS /COMENTS en All the Region III activities relative to
- (a) Monitor the licensee's trouble- troubleshooting / root cause activities have been
$ shooting activities completed and are documented in Inspection Reports t l '85-021,85-022 and 85-025.*
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- Inspection Report 85025 is in draft and will be issued in approximately I week.
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Other Activities All work on the new electric motor driven startup feedwater pump (SUFP) should be completed by early next week. Calibration of the associated instrumentation and testing of the system should also begin early next week. 9 Evaluations and inspections of 2155 safety system piping supports are continuing.
Nonconformance Reports (NCRs) have been written against 1594 of 1770 pipe supports inspected so far. Rework is required on 114 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 166 safety-related motor-operated valves onsite.
Of the 120 valves that have been tested, only a few will require retesting.
The lic.ensee is now repairing and testing valve motor operators continuously with three overlapping ten-hour shifts.
The licensee has performed engineering evaluations of the three hydraulic snubbers that did not meet the Technical Specification required Surveillance Test acceptance criteria. The evaluation revealed that although the snubbers required repair or adjustment they were operable. Therefore testing of additional snubbers is not required.
The NRC test review group has completed the preliminary review of the licensee's SRTP with satisfactory results. The draft Technical Evaluation Report (TER) will be sent to NRR next week. 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 activities. 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.
i ENCLOSURE L NOV 8 1985 5
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ITEMS ADDRESSED BY THE C0t911SSION - WEEK ENDING NOVEMBER 8, 1985 I
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j A. STAFF REQUIREMENTS - BRIEFING'ON STATUS OF SAFETY GOAL EVALUATION REPORT.
2:00 P.M., TUESDAY. OCTOBER 22. 1985 COMMISSIONER 5' CONFERENCE ROOM, D.C. l
! 0FFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to W. J. Dircks dated 11/5/85 l I The Commission met to discuss the status of the report " Safety ,
2 Goals for Nuclear Power Plants," NUREG-0880, which was issued '
- in 1982. -
l Conunissioner Each requested information as to why the staff has modified its position on averted onsite costs and the core melt i i design objective in the safety goal report.
j (EDO) (SECY Suspense: 11/15/85) ,
' t l The Commission requested staff to provide the Commission with a j list of questions or open issues to which the staff requires answers or guidance from the Commission in order to proceed !
with work on the safety goal report.
1 (EDO)
(SECY Suspense: 11/15/85) i The Conunission indicated that it would schedule a meeting in the near future with the Advisory Committee on Reactor Safeguards 4
(ACRS) to discuss the safety goal report.
! (Subsequently, the commission scheduled a meeting to discuss j the safety goal report and other items with the ACRS on
,
- Thursday, November 7 at 2:00 p.m.)
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l B. STAFF RECUIREMENTS - STATUS OF INTERPRETATION OF APPENDIX R - FIRE PROTECTION. 2:00 P.M.. THURSDAY. OCTOBER 3,1985. C0iWISSIONERS' CONFERENCE l - ROOM. D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to W. J. Dircks
! and H. H. E. Plaine dated 11/6/85 i
The Commission met with staff to discuss the status of the implementation of fire protection requirements, the fire i
protection rule contained in 10 CFR 50.48 and Appendix R and
! the staff's recommendations regarding implementation of Appendix i R contained in SECY-85-306.
The Commission requested a report from the staff on current fire protection enforcement actions as well as a suggested i schedule for affected licensees to comply with Appendix R l requirements.
l (IE/NRR) (SECY Suspense: 11/29/85) l ENCLOSURE O NOV 8 1985
T l
i B. CONTINUED l Chairman Palladino urged the Conunissioners to vote promptly on l l SECY-85-306. Additionally, he would like to see the staff :
1 incorporate a license condition in each facility license to j ensure enforceability of fire protection programs. This should l
- be done in addition to incorporating fire protection programs
! into the next edition of the FSARs. The license condition ;
i should allow flexibility which permits modifications of fire j protection programs in accordance with 10 CFR 50.59. :
)
i Commissioner Asselstine requested that OGC provide its comments !
i on staff's reply to the Trubatch memorandum on Appendix R -
- requirements.
j (OGC)
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(Subsequently, on October 24, 1985 the General Counsel provided 1 a response to the Commission.)
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} Commissioner Asselstine asked the staff to send to him the
- cost-benefit analysis required by the backfit rule of the new i or different interpretations of Appendix R. If such cost-
} benefit analysis does not now exist, he asked that the required
- backfit analysis be performed and sent to him before any new or modified interpretations are transmitted to licensees.
(NRR) (SECY suspense: 11/29/85) l .-
l C'. STAFF REQUIREENTS - DISCUSSION OF FITNESS FOR DUTY 10:00 A.M., TUESDAY, OCTOB ER 22, 1985. COPfil55 LONER 5' CONFER!!NCE ROOM. D.C. OFFICE (OPEN TO j
PUBLI; AIItNDANCE) Memo 5ECY to W. Dircts dated 11/8/85 j _
i i The commission met with the staff to discuss fitness for duty i for plant personnel in the nuclear industry.* ,
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i The Commission directed the staff to revise the policy state-
}' ment on fitness for duty to include broad objectives: the expectation that each utility will include provisions for j chemical testing in monitoring programs along with the expec- i i tation that each utility will develop a disciplinary program
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consistent with the EEI guidelines. This policy statement j should cover plant operating personnel as well as construction
! workers performing work in safety related areas.
(IE) (SECY Suspense: 11/21/85) i The Commission requested the staff to provide an analysis of the consequences to the health and safety of the public of having personnel unfit for duty at NRC licensed facilities
' other than power reactor facilities (i.e., fuel cycle facil-ities and research reactors) and discuss the role of NRC, if j any, in each case.
l (IE/NMSS) (SECY Suspense: 1/6/86)
ENCLOSURE O
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! NOV 8 1985
l C. CONTINUED 4
Commissioner Bernthal requested that the staff provide a list of utilities that have chemical screening programs and those that do not.
(IE) (SECY Suspense: 11/15/85)
- The Commission has under consideration a memorandum from Commissioner Bernthal dated October 31, 1985, subject " Fitness for Duty Policy Statement" (COMFB-85-16), a copy of which was provided to the staff.
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ENCLOSURE O NOV 8 1985
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- NRR MEETING NOTICES
- m NOVEMBER 8, 1985 DOCKET APPLICANT /
DATE/ TINE NtMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 11/12/85 P-110 To discuss auxiliary actuating Vortech F. Cherny 10:00 am Bethesda devices for PWR Safety Valves which have been proposed for use in France 11/12-15/85 50-443 PSNH Seabrook Off. To discuss technical specifi- Public Serv. of V. Nerses 50-444 7910 Woodsont Ave. cation review of Seabrook's New Hampshire Bethesda, Md. proposed tech specs
! 11/13-14/85 50-247 Reg. I office To discuss Inservice Testing Consolidated Edison M. Slossen
- 9
- 00 am King of Prussia, Program for Indian Point 2 i PA
! 11/14-15/85 50-315 Donald Cook site To discuss wrong unit / wrong Indiana and Michigan D. Wigginton i 9:00 am 50-316 Stevensville, Mich. train events at Cook for use Elec. Co. '
l in developing industry guidance for prevention 11/15/85 50-280 P-114 To discuss Appendix R Exemption Virginia Electric & T. Chan 9:00 am 50-281 Bethesda requests Power Co.
(Surry) 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
- Copies of summaries of these meetings will be made publicly available and placed in the respective docket file (s) la the NRC and local public document rooms l 8
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g NRR MEETING NOTICES
- DOCKET APPLICANT /
DATE/ TIME NLSSER LOCATION PURPOSE ATTEMEES NRR CONTACT 11/18-19/85 50-245 Millstone Site Review M-1 IPSAR, ISAP, and ACRS J. Shes Waterford, Conn. FTOL-SER Conversion Northeast Nuclear Energy Co.
4 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 defennents from Cycle 11R outage in the operating Cycle 11 - Dyster Creek 11/21/85 50-400 Shearon Harris Environmental qualification Carolina Power & 8. Buckley 3:00 pm Site audit Light Co.
i j Copies of summaries of these meetings will be made publicly available and placed in the respective docket file (s) ia the NRC and local public document rooms.
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HMSS KETING NOTICES
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. FOR WEEK ENDING: 11/8/85 h Division cf Fuel Cycla rnd Materini Safcty .
oo DOCKET - ATTENDEES /
NUpBER PURPOSEf APPLICANT NRC CONTACT LOCATION gDATE/ TIE 11/4-15/85 70-1257 San Francisco. To attend ANS meeting. G.381dinger (FC) Bidinger CA Richland WA Discuss dry UF6 Process'and G. Bidinger (FC)
Accompany Inspector at Exxon. RV Inspector Exxon Reps 11/6/85 70-143 Atlanta, GA To meet with Region II staff W. Crow (FC) Crow '
and discuss NFS license renewal A. Soong (FC) application. RI! staff 11/12/85 71-9202 Willste Discuss rev!ew of spent fuel C. MacDonald (FC) MacDonald Room 106 cask for use at West Valley, R. Odegaarden (FC) .
New York. R. Chappell (FC)
K. Goldmann (Transnuclear)
11/18/85 72-3 Willste To discuss Carolina Power & D. Koss, et al. (CP&L) Roberts 5th floor Light Co. (CP&L) responses to J. Roberts (FC) conf room NRC questions regarding CP&L F. Sturz (FC) dry storage application for the J. Schneider (FC)
H.B. Robinson site.
11/18-20/85 Project West Valley, Visit to West Valley to discuss T. Clark (FC) Clark M-32 NY QA responses, LLW fom test T. Johnson (WM) data and SAR review. R. Person (WM)
Reps of West Valley -
11/18-21/85 Atlanta, GA To attend two DOE meetings: Fall J. Cook (FC) Cook W. Thompson (FC)
Info. Meeting of the Office of Civilian Radioactive Waste Manage- Reps of DOE ment and a workshop to discuss m planning for transportation y under NWPA.
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- l MMSS K ETING NOTICES FOR WEEK ENDING: 11/8/85.
l = Division of Fuel Cycl 7 cnd Materl71 Safcty page 2 ,
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I co DOCKET , ATTENDEES /
MPOSE. APPLICANT NRC CONTACT NUfBER LOCATION gDATE/ TIE l
11/19/85 Baltimore, 2 Presentation at Johns Hopkins R. Cunningham (FC) Cunaingham 8:30 am University - Seminar on Low-Level '
Waste - Under the auspices of '
CARER.
Division of Safeguards None Division of Waste Management Noveder 18-19 Atlanta, GA Information Management NStill NStill i Meeting (Fall) DOE staff with DOE /0ffice of Civilian Radioactive Waste Management P
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E RES t1EETING NOTICES November 8,1985 DOCKET ATTENDEES /
_, DATE/ TIE NUPEER LOCATION PURPOSE ,
APPLICANT NRC CONTACT E
11/13-14/85 Sandia Lab., A Conference on Security Vehicle Ten Eyck,NMSS Ting Albuquerque,NM Ting,RES t
l 11/14/85 LANL, Los Alamos Contract reviews (vital equipment / Ting, RES Ting
, area identification techniques & LANL personnel i non-destructive reference book) t 11/18-22/85 CEA Hdqs HYDROCOIN workshop and coordination International Nicholson Paris, France group meeting govemment agencies &
contractors dealing w/ ground- >
water modeling for HLW & LLW facilities l 12/2-4/85 TBD Review the needs for validation of RES contractors Randall l 1/27-29/85 mathematical models for waste and selected repository licensing in workshon individuals by format invitation l
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November 8, 1985 g OSP MEETING NOTICES
- PURPCSE ATTENDEES NRC CONTACT DATE/ TIME LOCATION e
- Bethesda, Md. Meeting with Illinois Illinois-T. Lash DNussbaumer 11/15/85 to discuss Sec. 274b and staff Agre(ment NRC-0SP, NHSS &
ELD Staff New York, NY Attend National Association PUC Representatives JSaltzman 11/18/85 of Regulatory Utility Connissioners (NARUC)
Annual Convention 11/18-22/85 Austin, Texas Technical Review Committee State and Federal LBolling ideeting on the Suggested Agency Representa-State Regulations tives 11/19/85 Farmington, CT Discuss issues concerning ANI Representatives JSaltzman Price-Anderson with American Nuclear Insurers (ANI)
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E AE00 MEETING NOTICES oo 5 PURPOSE ATTENDE25 NRC CONTACT "DATE/ TIME LOCATION To collect and dis- Stuart Rubin (AE00) E. Leeds 11/19/85 Maine Yankee 9:00 a.m. Atomic Power cuss information con- Eric Leeds (AE00)
Plant cerning the instrument air' supply to the tem-perature control valves in the component cooling system which supplies cooling to both Emergency Diesel Generators.
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