ML20135H390

Weekly Info Rept for Wk Ending 850913

ML20135H390
Person / Time
Issue date:	09/18/1985
From:	Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To:
References
WIR-850913, NUDOCS 8509230202
Download: ML20135H390 (38)

Text

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I September 18, 1985 l

For: The Commissioners t

From: T. A. Rehm, Assistant for Operations, Office of the E00

Subject:

WEEKLY INFORMATION REPORT - WEEK ENDING SEPTEMBER 13, 1985 i A summary of key events is included as a convenience to those Commissioners who may prefer a condensed version of this report.

Contents Enclosure

, Administration A Nuclear Reactor Regulation B Nuclear Material Safety and Safeguards C

! Inspection and Enforcement D Nuclear Regulatory Research E Executive Legal Director F*

l International Programs G

! State Programs H*

1 Resource Management I*

Analysis and Evaluation of Operational Data J

Small & Disadvantaged Business Utilization & Civil Rights K*

Regional Offices L CRGR Monthly Report -

M* ,

Executive Director for Operations N* .

1 Items Addressed by the Commission 0*

i Meeting Notices P Proprietary or Other Sensitive Information (Not for Q externaldistribution) i i *No input this week.

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// J 2 l 85092'30202 8 g 8 T. A. Re .m Assistant for Operations

[ORRESOpeENCEPDR Office of the Executive Director for Operations

Contact:

T. A. Rehm, EDO j 492-7781

i HIGHLIGHTS OF WEEKLY INFORP.ATION REPORT 4 . WEEK ENDING SEPTEMBER 13, 1985 '

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Davis-Besse Nuclear Power Station On September 6, 1985, the licensee inadvertently overpressurized the '

i No. I steam generator (SG) when the plant was in cold shutdown. The i problem occurred as a result of personnel error while the licensee was i testing the No. 1 auxiliary feedwater pump. A partially open feedwater i discharge valve allowed feedwater to flow to the already full SG which

} was in wet layup. The maxfmum pressure reached was about 1050 psig at i a temperature of about 100 F. Plant Technical Specifications require

that if a SG pressure gf greater than 237 psig is reached at temperatures below 110 F, an engineering evaluation of the structural integrity of the SG must be performed.

i Prior to conducting the auxiliary feedwater pump test, the discharge

~

valve was deenergized in the closed position. However, when tagging . :

the valve, the operator did not verify that the valve was closed and ,

consequently failed to detect that the valve was slightly open. When  !

the SG was inadvertently pressurized, the operators received a SFRC_S  :

i  !

trip. The operators, believing that the SFRCS signal was not related j to the pump test repeated the pump test cycle at least one additional ,

time.

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The licensee is presently performing the engineering evaluation. No ,

further activities on the No.1 SG will be conducted pending review of '

the licensee's engineering evaluation and'the SG pressure record by the Resident Inspector. No. 2 SG was not affected.

l Three Mile Island. Unit 1 (TMI-1) +

i On Saturday, September 7,1985, at approximately 3:58 p.m., there was a l fire in the control rod drive cabinet at TMI-1. The reactor was in hot j shutdown and technicians were conducting rod testing with the shutdown  ;

l banks fully withdrawn. Rods were being transferred to an alternate '

power supply when a smoke alarm was received in the control room and a l 1 security guard reported arcking in a control rod drive cabinet. A  ;

manual trip was initiated and the rods inserted in a normal fashion. A ,

CO., fire extinguisher was discharged in the CRDM cabinet. The fire was '

out in approximately 6-7 minutes.

Damage was done to at least 3 of 68 transfer switches and their f i associated wiring. The cause of the fire is unknown and the licensee '

! is conducting detailed trouble shooting at present. Once the cause of r

! the event is determined, physical repairs are nut expected to require  ;

'j extensive time to complete.

,t Part 21 Report i Morrison-Knudsen notified NRC Headquarters by phone September 9, i 1985 of a problem apparently found at Sequoyah with a Bruce /GM Emergency Diesel Generator. The problem concerns the engine i governor actuator electrical connecting plug. The threads

! between the plug adaptor and the fitting of the flexible hose '

do not match. Vendor will followup with written report within 4

5 days. So far Sequoyah is the only identified site.

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! SEP 131985

, - - , , yo ,+r- , - - ,v-- r - , ,-w,v+wm--.-e,,,,,-e-, .-y n , -w-+r w-.e--, .m v ----n--.---m-.-----v,------wwn-,.-g,n- y .,w- --n--e----m,

J_-- --.w.- .4 0FFICE OF ADMINISTRATION Week Ending September 13, 1985 4

i ADMINISTRATION OF THE FREEDOM 0F INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision i

Carryovers,1984 179 23 Received, 1985 626 39 Granted 504 26 Denied 136 14 Pending 165 22 ACTIONS THIS WEEK Rect'ved i Roanne Sragow, Requests a copy of the current design plan (as of Lack & Sragow February 28,1985) for the McGuire nuclear power plant, (85-621) specifically the a.rea where the reactor building fuel handling manipulator crane was located on February 28.

Lyle Graber, Requests a copy of an August 1985 memo from Victor i NUS Corporation Stello to William Dircks, " Meeting Minutes from CRGR

(85-622) Meeting Number 79 with enclosures."

Paul . Gardner, Requests a copy of the A,,ril 7,1980, report, " Evaluation

, Missouri Public and Audit of the Wolf Creek Generating Station for Daniel Service Commission Construction Company."

(85-623) 1 -

4 Bruce W. Stainbrook, Requests a copy of the radiation license for Carr I Becton Dickinsun Scarborough of Decatur, Georgia. I (85-624)

Wanza L. Paine, Requests a copy of the NRC's telephone directory.

Jefferson Financial 1 i Services Corp.

(85-625)

(Anindividual Requests records pertaining to himself that are requesting maintained by the NRC.

information about himself)

(85-626)

CONTACT: J. M. Felton i 492-7211 ENCLOSURE A 4

SEP 131985

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.e Received, Cont'd i J. Patrick Hickey, APPEAL TO THE COMMISSION for the release of denied Shaw, Pittman, records concerning the William H. Zimmer nuclear Potts and power plant.

Trowbridge 4

(85-A-39-83-684)

Granted 4

Joseph J. Holonich, In response to a request for records indicating the

, International number of inspection manhours expended on an annual Energy Associates, basis for Peach Bottom Units 2 and 3 and the Limerick i Ltd. plants from 1970 through 1980, made available a copy (85-466) of a record providing the requested information.

Nina Bell, In response to a request for two categories of records 4

Nuclear Information regarding NUREG/CR-3817, " Development, Use and Control of and Resource Maintenance Procedures in Nuclear Power Plants: Problems Service and Recommendations," informed the requester that the NRC (85-494) is not in possession of the records subject to this request.

Nan M. Seuffert, In response to a request for all records regarding tests Environmental done in the vicinity of the Oyster Creek nuclear power Task Force plant for radiation in air, soil or water, and the (85-531) results of those tests, made available three records.

Informed the requester that additional records subject to ,

i this request are already available at the POR.

l Nancy E. Pearson, In response to a request' for a copy of SECY-85-129, made Stone and Webster available a copy of the requested paper.

Engineering Corp.

t (85-532)

Thomas C. Houghton, In response to a request for copies of certain Reactor KMC, Inc. Operator and Senior Reactor Operator license examination (85-559) questions and answer keys, made available 15 records.

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! Stephanie Dematitis, In response to a request for nine categories of Data Base, Inc. information concerning data processing centers operated

. (85-585) by the NRC, made available a copy of a reccrd providing the requested information.

~ Billie P. Garde. In response to a request for copies of all records t j Government regarding IE Information Notice 85-66, made available

! Accountability seven records.

! Project (85-590)

John Lapp, In response to a request for copies of the bid abstract for Invitation for Bid No RS-ASB-85-401, made available Neal R. Gross and i Co., Inc. two records.

(85-592)

ENCLOSURE A

SEP 131985 i

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• Granted, Cont'd /

Michael F. Crook, In response to a request for the approved operational Envirotronics nuclear license for Nuclear Metals. Inc., of Concord, (85-597) Massachusetts, made available 12 records.

Cecil Lue-Hing, In response to a request for a list containing the The Metropolitan names and addresses of NRC licensees located in Cook Sanitary District County, Illinois, made available a printout furnishing of Greater Chicago the requested information.

(85-607)

Frank Tankersley, In response to a request for a list of licensed Frank Tankersley reactor operators, made available a copy of the requested Associates, Inc. list.

(85-618)

(Anindividual In response to a request for records pertaining to requesting himself that are maintained by the NRC, informed the information about requester that the NRC has no records pertaining to him himself) in its radiation exposure, document control, or the (85-626) security systems of records.

Denied C. Coleman Bird, In response to a request for a copy of Contract No.

Wald, Harkrader NRC-17-85-207, all records relating to this contract, and Ross and records relating to the termination of NRC contract (84-853) No. SECY-84-327 and any discussions or negotiations with any providers of stenographic reporting servic'es upon, or at any time af ter, the termination of this contract, made available 70 records. Denied eight records in their entirety and portions of 15 records because they contain commercial and fintncial information on companies conducting business with the NRC, the release of which could cause competitive harm to these companies, or they are predecisional in nature and contain information created and considered during the deliberative process of evaluating proposals, forming and exchanging opinions, and making recommendations and decisions concerning contract award, contractor performance, and contract termination.

Lynne Bernabei, In response to a request for three categories of.

Government records relating to the Waterford Steam Electric Accountability Station, Unit 3, made available 51 records. DenieJ Project portions of eight records pursuant to Exemptions 5, (85-123) 6 and 7C. Denied over 500 records in their entirety pursuant to exemptions 5, 6, 7A, 70, and 70. Informed the requaster that additional records subject to this request are already available at the PDR.

ENCLOSURE A SEP 131985

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-Denied, Cont'd i Billie P. Garde, In respose to a request for all records relating to I

Government Inspection Report 83-09 on the Braidwood nuclear power Accountability plant, made available 25 records. Informed the requester Project that additional records subject to this request are (85-452) 'already available at the PDR Denied five records in .

i their entirety, release of which would tend to inhibit the open and frank exchange of ideas essential to the 4

deliberative process. l 1

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ENCLOSURE A SEP 1 S G85 i

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WEEKLY INFORMATION REPORT DIVISION OF CONTRACTS WEEK ENDING SEPTEMBER 13, 1985 RFP ISSUED RFP No.: RS-SEC-86-201

Title:

" Stenographic Reporting Services"

Description:

Contractor will provide stenographic reporting services for NRC Commission Meetings held in the Washington, D.C.

Metropolitan Area.

Period of Performance: 2 years with an option to extend one additional year.

Sponsor: Office of the Secretary Status: RFP issued on September 6, 1985. Proposals due October 7, 1985.

PROPOSALS UNDER EVALUATION l RFP No.: RS-0IE-85-159

Title:

"NRC Training Courses for Inspectors and Engineers"

Description:

The contractor will provide experienced instructors and other experts to conduct 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 and Codes."

Period of Performance: One year with 3 one-year options.

Sponsor: Office of Inspection and Enforcement Status: RFP closed on September 6, 1985. Proposals forwarded to Source Evaluators for review on September 10, 1985. Competitive range to be established on October 31, 1985.

RFP No.: RS-01E-85-158

Title:

" Technical Assistance in Developing and Implementing Programs and Procedures for Inspection of Operating Reactors During Major Outages."

Description:

The objective of this project is to provide technical assistance to the NRC for activities pertaining to planned outages of

{ operating reactors. This includes the development of standardized inspection procedures for planned outages as well as providing assistance to the regional offices for conducting inspections during planned outages of operating reactors.

Period of Performance: 3 years Sponsor: Office of Inspection and Enforcement Status: RFP closed on September 10, 1985. Proposals forwarded to Source Evaluators for review on September 12, 1985. Competitive range to be established on October 11, 1985.

2 RFP No.: RS-RES-84-Il4

Title:

" Groundwater and Transport of Contaminants through Saturated Fractured Geologic Media from High Level Radioactive Waste (HLW)"

Description:

Provide NRC with research products which may support and/or confirm the basis for technical positions on the above subject related to groundwater flow and transport in saturated fractured rocks in which HLW might be stored.

Period of Performance: 3 years Sonsor: Office of Nuclear Regulatory Research ENCLOSURE A Status: Final Evaluation Report received on September 9, 1985.

SEP 1 o 1985

0FFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending September 13, 1985 Three Mile Island, Unit 2 The Pennsylvania Department of Health has issued a report which concludes that there is no evidence of increased cancer among residents .

attributable to the March 28, 1979 TMI-2 accident. The study covered cancer deaths recorded from 1974 through 1983 within 20 miles of TMI, 1 as well as new cancers from July 1982 through June 1984 in areas

" downwind" of TMI during the accident. The study found that there is no statistically significant difference between recorded cases and what epidemiologists would have expected had the accident never occurred.

The report is described by the State Health Secretary, Dr. H. Arnold Muller, as the "first scientific analysis of cancer among those living within a 20-mile radius of the plant," noting that the latency period for most cancers would have made any earlier effort " premature." There is also ne indication of a significant increase in leukemia, which has a shorter latency period.

The report includes a critique of a survey, conducted by Normarrand l Marjorie Aamodt, which claimed a dramatic rise in cancer deaths

! " clearly tied to the TMI-2 accident." Dr. Muller said that the Aamodt survey conclusions are " contrary to scientific findings." The Health Department's study revealed that cancer deaths which the Aamodts attributed to TMI included cancers diagnosed prior to the accident and cancer cases among people who moved into the area after the accident.

The study also revealed that the Aamodt study was " biased" in its selection of survey subjects. ,

River Bend 4

By September 6,1985, the licensee, Gulf States Utilities had loaded 200 fuel bundles into the River Bend core. By September 9, GSU had transferred an additional 200 fuel bundles from the fuel building into containment. GSU expects to commence loading these additional 200 fuel i bundles, today. GSU currently projects completion of loading all 624 fuel bundles by September 21, 1985 with initial criticality by September 29, 1985.

On September 4,1985, River Bend received two reactor trip signals.

These trips were the results of inadvertent manipulation of an out-of-service main steam line radiation detector by contractor personnel and a subsequent error in electrically isolating the

, radiation detector.

1 ENCLOSURE B SEP 131985

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. North Anna Power Station, Units No. 1 & No. 2 (NA-1&2)

On July 13,1982, VEPC0 applied for an amendment to revise the operating licenses of NA-1&2 to permit the receipt and storage of 500 spent fuel assemblies from the Surry Power Station, Units 1&2. The request was opposed by the Concerned Citizens of Louisa County (CCLC) and has been the subject of ASLB prehearing conferences, discovery, oral arguments, prehearing briefs and an evidentiary hearing which took place on May 21-22, 1985 in Charlottesville, Virginia. These matters were specified as CASE OLA-1 by the ASLB.

By Board Order dated September 3, 1985, the ASLB has concluded that the Director of NRR is authorized to issue amendments for NA-1&2 to permit the receipt and storage of 500 spent fuel assemblies from Surry 1&2.

The Board's initial decision became effective immediately upon issuance. Therefore, the staff has begun the processing of the applicable amendments.

In a companion case, OLA-2, wherein VEPC0 applied for an amendment to the NA-182 operating licenses to permit the expansion of the spent fuel pool storage capacity, the ASLB rejected the proposed contentions of CCLC, denied its petition for leave to intervene, dismissed the case and authorized the issuance of amendments which took place on December 21, 1984.

Arkansas Nuclear One, Units 1 and 2 (ANO-182)

In our Daily Highlight dated July 18, 1985, we reported that Arkansas Power & Light Company (AP&L) was facing a severe financial crisis as AP&L had to pay its share of the construction costs of Grand Gulf beginning August 1985 at $30 million a month without getting rate relief for Grand Gulf from the Arkansas Public Service Commission (APSC). We have been informed by AP&L that the APSC, on September 9, 1985, has granted a rate relief of $81.1 million a year. AP&L originally asked for a $264 million increase a year. AP&L indicated that the company would continue substantial cost curtailment for the foreseeable future. AP&L has assured the 4RC that the cost curtailment program would r,ot affect the safe operation of ANO-1&2 and the comitments to the NRC. The NRC will be monitoring the effects of the cost curtailment program closely.

Davis-Besse Nuclear Power Station On September 6, 1985, the licensee inadvertently overpressurized the No.1 steam generator (SG) when the plant was in cold shutdown. The problem occurred as a result of personnel error while the licensee was testing the No. I auxiliary feedwater pump. A partially open feedwater discharge valve allowed feedwater to flow to the already full SG which was in wet layup. Themaxfmumpressurereachedwasabout1050psigat a temperature of about 100 f. Plant Technical Specifications require that if a SG pressure gf greater than 237 psig is reached at temperatures below 110 F, an engineering evaluation of the structural ENCLOSURE B integrity of the SG must be performed.

SEP 131985

1 Prior to conducting the auxiliary feedwater pump test, the discharge valve was deenergized in the closed pcsition. However, when tagging the valve, the operator did not verify that the valve was closed and

! consequently failed to detect that the valve was slightly open. When the SG was inadvertently pressurized, the operators received a SFRCS trip. The operators, believing that the SFRCS signal was not related to the pump test repeated the pump test cycle at least one additional time.

The licensee is presently performing the engineering evaluation. No i further activities on the No.1 SG will be conducted pending review of the licensee's engineering evaluation and the SG pressure record by the Resident Inspector. No. 2 SG was not affected.

I Three Mile Island, Unit 1 (TMI-1) i i On Saturday, September 7, 1985, at approximately 3:58 p.m., there was a

! fire in the control rod drive cabinet at TMI-1. The reactor was in hot  ;

shutdown and technicians were conducting rod testing with the shutdown l banks fully withdrawn. Rods were being transferred to an alternate power supply when a smoke alann was received in the control room and a security guard reported arcking in a control rod drive cabinet. A

manual trip was initiated and the rods inserted in a normal fashion. A j CO,, fire extinguisher was discharged in the CRDM cabinet. The fire was

+

out in approximately 6-7 minutes, i

Damage was done to at least 3 of 68 transfer switches and their

associated wiring. The cause of the fire is unknown and the licensee I is conducting detailed trouble shooting at present. Once the cause of the event is determined, physical repairs are not expected to require extensive time to complete.

Three Mile Island, Unit 1 (TMI-1) Appeallate Court Rehearing Petitions 3 On August 27, 1985, the 3rd U.S. Circuit Court of Appeals issued a l judgement that denied the petition for review of the Comission's

]

decision lifting the imediate effectiveness of the 1979 shutdown order

on TMI-1 and affirmed the Comission's Order CLI-85-9 dated May 29, l 1985. On August 29, 1985, the Panel ordered that the existing stay

, preventing restart is to remain in effect until disposition of motions L i for rehearing. No extensions of time will be permitted, i.e., parties seeking rehearing have until September 10 to file. Only parties

seeking a rehearing are to file motions at this time.

TMI-A, UCS, and the Comonwealth of Pennsylvania have all petitioned

' for rehearing in accordance with the Appeal Court's procedures. To

. date, no word has been received by the staff regarding whether the Aamodts will also file a petition. Under the normal appeal court's i procedures, a vote will be taken by approximately September 18, 1985 which could go one of at least three ways: (a) yes, a rehearing will i be held, (b) motions for rehearing are denied, or (c) the Court decides ENCLOSURE B to obtain responses to the petitions for rehearing from the licensee and NRC or other pertinent parties. Of course, the Coart could decide to change its normal procedures for this particular case.

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SEP 131985

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Limerick i Oral argument on the appeals of the intervenors regarding the Licensing l

Board's May 2, 1985 third partial initial decision dealing with offsite

emergency planning will be heard on October 11, 1985 before the Appeal Board.

< The plant is at 23% power _ (144 MWe) while the licensee conducts feedwater system tuneup tests. Recent tests have included cycling of the safety / relief valves, and turbine tripping. Near future tests will include shutting the plant down from the remote shutdown panel and a loss-of-offsite power test.

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NRC TMI PROGRAM OFFICE WEEKLY STATUS REPORT WEEK ENDING SEPT' EMBER 13, 1985 1

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1. 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

'i shallow ends of the fuel transfer canal. The deep end is filled with water to a depth of about 20 feet (about 5 feet above the top of the plenum).

The modified internals indexing fixture is installed on the reactor vessel flange and is flooded to elevation 327 feet 6 inches (151 -

feet above the top of the core region).

Calculated reactor decay heat is less than 12 kilowatts.

RCS cooling is by natural heat loss to the reactor building ambient atmospnere. Incore thermocouple readings range from 70*F to 91*F with an average of 79'F. Average cold leg temperature is 54*F.

The average reactor building temperature is 58'F. The reactor building airborne activity is 1.0 E-8 uCi/cc Tritium and 2.8 E-10

) uti/cc particulate, predominantly Cesium 137.

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2. WASTE MANAGEMENT 1

The Submerged Demineralizer System (SDS) was shutdown during this period.

EPICOR II ccmpleted processing batch 265, which was about 59,000 gallons from Condensate Tank 1A (C0T-1A).

Total volume processed through SDS to date is 2,963,375 gallons, and 1 the total volume processed through EPICOR II is 2,606,982 gallons.

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ENCLOSURE B SEP 131985

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3. DOSE REDUCTION / DECONTAMINATION ACTIVITIES

- Decontamination activities are continuing on the 281' level of the auxiliary building.

- The licensee recently released about 2,000 square feet of the auxiliary building from contamination control and has exceeded the 1985 decontamination goal of 10,000 square feet in the auxiliary building.

- Average general area radiation dose rate is 40 mrem per hour on the 347' level of the reactor building and is 67 mrem per hour on the 305' level of the reactor building.

4. ,EIRONMENTALMONITORING

- EPA sample analysis results show TMI site liquid effluents to be in accordance with regulatory limits, NRC requirements, and the City of Lancaster Agreement.

- TMI water samples taken by the US Environmental Protection Agency at the plant discharge to the river consisted of seven daily composite samples taken from August 24 to August 31, 1985. One 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> composite sample taken between August 29 and 30, 1985 detected 3 E-9 uCi/cc of Iodine-131. Essentially the same concentration of Iodine-131 was detected by an upstream sampler. This indicates that the Iodine-131 was taken into the plant from the river and the plant was not the source. No reactor related activity was detected. The detected concentration of Iodine-131 was 1% of the NRC allowable limit for release to unrestricted areas.

- The Lancaster water sample taken at the water works intake and analyzed by the US Environmental Protection Agency consisted of a seven day composite sample taken from August 25 to August 31, 1985.

A gamma scan detected no reactor related radioactivity.

- The NRC outdoor airborne particulate sampler at the TMI Site collected a sample between September 4 and September 11, 1985. No reactor related radioactivity was detected. Analysis showed I-131 and Cs-137 concentrations to be less than the lower limits of detectability.

5. REACTOR BUILDING ACTIVITIES

- Work continued on installation of the defueling tool racks.

- Defueling Water Cleanup System (DWCS) preoperational testing and modification continued.

- Installation of cable tray shielding continued.

- Preoperational testing of the reactor building sump recirculation system components is in progress. Two of the three pumps failed the precperational test and the pump vendor hts been called to assist ir, troubleshooting.

1 ENCLOSURE B SEP 131985

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! 6. AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES Installation of the DWCS continued. Partial DWCS turnover for processing RCS durii.g early defueling is expected to be completed in late September.

All four of the fuel canister storage racks have been delivered to the THI site. Inspections by GPU personnel identified cracks in several structural welds in the first two of the racks where the racks had engaged the shipping dunnage. Liquid penetrant examination of similar welds in the third fuel canister rack did not identify any crack indications. The fourth fuel rack is currently being inspected. Further inspections and repair of the racks is in progress at the site. A completion date has not been established. ,

7. NRC EVALUATIONS IN PROGRESS Technical Specification Change Requests numbers 48, 49, and 50.

Recovery Operations Plan Change numbers 29, 31, and 32.

Fuel Canister Technical Evaluation, Revision 1.

Defueling Safety Evaluation.

Application for seismic exemption.

SDS Technical Evaluation and System Description Update.

• Core Stratification Sample Safety Evaluation.

) -

Heavy Load Handling Safety Evaluation Report.

8. PUBLIC MEETING On the evening of September 11, 1985, the Advisory Panel for thL Decontamination of Three Mile Island Unit 2 held a public meetirg at the House of Delegates Office Building in Annapolis, Maryland. At this meeting, the Panel received a status report on the defueling program by 1

Mr. Frank Standerfer, Vice President / Director, GPU Nuclear Corporation.

Mr. Standerfer also provided an update on the cleanup funding situation.

Mr. Frank Miraglia, Deputy Director, Division of Licer. sing, NRR, and Dr.

Bernard J. Snyder, Director, TMIP0:NRR, described the NRC plan for the reorganization of the Office of Nuclear Reactor Regulation (NRR) and discussed the resulting changes in the TMI Program Office.

Dr. Willis Bixby, manager, DOE TMI site office, provided an overview of DOE's role in the cleanup.

Dr. William Kirk, Director, TMI Field Station, EPA, provided a summary of environmental monitoring in the vicinity of TMI.

1 Dr. Tom Magette, Director of the Maryland Power Plant Siting Program, discussed environmental monitoring of the Susquehanna River conducted by his office.

ENCLOSURE B SEP 131985

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4 Mr. Jack Devine, GPUNC, presented -information on the status of processed +

water generated during the cleanup and provided the licensee's schedule for determining the ultimate disposition of the water.

! The next meeting of the Advisory Panel is scheduled for October 1985 in j Harrisburg, Pennsylvania. Exact date and location for this meeting will

} be announced at a later date.

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ENCLOSURE B SEP 131985 .

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6 0FFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest ,

Week Ending September 13, 1985

, Near Term NRC Actions Under the Nuclear Waste Policy Act Section: 114(e) of NWPA: Cooperation on Preparation of Project Decision Schedule.

Action:

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! DOE has requested comments on tne draft Project Decision Schedule by September 13, 1985.

l Status: Proposed staff comments were transmitted to the Commission on August 21, 1985 for their approval and submittal to 00E.

Section: 114(f) of NWPA: Preliminary Determination of site suitability.

. Action: As stated in the final Mission Plan submitted to Congress, and the Draft Project Decision Schedule, DOE plans to make a i preliminary determination of site suitability upon recommendation of the three sites to the President, now scheduled for November, 1985. The Commission met with representatives of States and Tribes on Friday, September 6, 1985 to receive their views on preliminary determination.

Status: The Commission has not reached a decision on its oosition

concerning preliminary determination.

Section

134 of NWPA: Hybrid Hearings Action: A final rule establishing procedures for expansion of onsite spent fuel storage capacity or transshipment of fuel was submitted to the Commission on July 8, 1985.

Status: The Commission voted to approve the rule on September 5, 1985. -

The final rule is expected to be published in the Federal Register soon.

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ENCLOSURE C l SEP 1319o5

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Foreign Visitors On September 10, 1985, representatives of NMSS, IE, and RES met with Dr. Roger Clarke and Mr. Geoff Webb of the National Radiological Protection Board, United Kingdom, to discuss issues related to the revision of 10 CFR Part 20,

exemption levels, and waste management. One of the primary topics was the way in which the United States, and NRC in particular, was implementing the

, recommendations of the International Commission on Radiological Protection on dose limits and waste management.

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ENCLOSURE C

( SEP 121985 r

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r OFFICE OF INSPECTION AND ENFORCEMENT Items of Interest Week Ending September 13, 1985

1. The following Significant Enforcement Actions were taken during the past week:

a. EN 85-60, a Notice of Violation and Proposed Imposition of Civil Penalties in the amount of $16,000 was issued to Calumet Testing Services, Inc. (Griffith, IN). This action is based on an over-exposure greater than 75 rems to the hand of a radiographer. Associ-ated with this violation were two others involving the failure to perform _a survey and the use of unsupervised personnel in performing radiography,

b. EN 85-61, a Confirmatory Order was issued September 11, 1985 to Christ Hospital (Cincinnati, OH). The Order is an immediately effective Order which confirms the licensee's commitment to implement

, a new procedure to prevent future medical therapy misadministrations.

2. The following IE Preliminary Notifications were issued during the past ,

week:

a. PNO-I-85-63, Conemaugh Valley Memorial Hospital (Johnston, PA), Lost Iodine-131 Capsules.

b. PNO-I-85-64A, Public Service Electric and Gas (Hope Creek),

4 September 1985 Carbon Dioxide Discharge (Update).

c. PNO-I-85-65, Monmouth Medical Center (Long Branch, NJ), Lost Xenon-133 Ampules.

d. PNO-I-85-66, GPU Corporation (TMI Unit 1), Fire in Control Rod Drive Power Distribution Panels.

e. PNO-II-85-87, Florida Power Corporation (Crystal River Unit 3),

Outage in Excess of 48 Hours.

f. PN0-II-85-88 Florida Power and Light Company (St. Lucie Unit 2),

Unscheduled Shutdown Longer Than 48 Hours.

g. PN0-II-85-89, Virginia Electric and Power Company (North Anna Unit 1),

Unscheduled Shutdown Greater Than 48 Hours.

h. .PNO-III-85-79, Northern States Power Company (Prairie Island), Bomb

. Threat.

1. PNO-III-85-80, Toledo Edison Company (Davis-Besse), Overpressuriza-tion of a Steam Generator.

j.. PNO-III-85-81, Dowser-Morner(Dayton,OH),StolenTroxlerGauge.

ENCLOSURE D SEP 151985

k. PNO-IV-85-44C, Saskatchewan Mining Development Corporation (Saskatoon, Saskatchewan, Canada), Truck-Train Accident Involving Spread of Uranium Concentrates (Final Update).

1. PN0-V-85-57, Southern California Edison, Inc. (San Onofre Unit 2),

Shutdown Greater Than 48 Hours Due to a Fire in the Turbine Generator Enclosure.

3. The following IE Information Notices were issued during the past week:

None.

4. Other Items

a. ASQC Meeting Director, IE, presented a speech at the Twelfth Annual National Energy Division Conference of ASQC in Knoxville, TN on September 9, 1985. Chief, Reactor Construction Program Branch, Division of 1 Inspection Programs also attended the conference.

b. Senior Management Meeting Deputy Director, IE was at the Davis-Besse site on September 9, 1985 for a senior management meeting.

c. Construction Appraisal Team (CAT) Inspection Representatives of Reactor Construction Program Branch, Division of Inspection Programs and NRC consultants continued the CAT inspection at Byron Unit 2 this week. Inspection is scheduled to continue to September 20, 1985. Exit meeting with the licensee is scheduled for Friday, September 20, 1985.

d. Nuclear Transportation Representative of Safeguards Materials Program Branch, Division of Inspection Programs was in Richland, WA cn~ September 9, 1985 to pre-sent a lecture during the Office of State Programs training course on Nuclear Transportation for State Personnel,

e. Part 21 Report (1) Morrison-Knudsen notified NRC Headquarters by phone September 9, 1985 of a problem apparently found at Sequoyah with a Bruce /GM Emergency Diesel Generator. The problem concerns the engine governor actuator electrical connecting plug. The threads between the plug adaptor and the fitting of the flexible hose do not match. Vendor will followup with written report within 5 days. So far Sequoyah is the only identified site.

ENCLOSURE D SEP 131985

(2) General Electric made a telephone report to this office on August 30, 1985 when they experienced three test anomalies of Reliance Class RHAC motors during environmental qualifica-tion testing of the Limitorque fast acting SB-3-150 valve motor operator for Gulf States Utilities and Niagra Mohawk.

This raised concerns with the long term (100-day) availability of valve operator motors with magnesium rotors. GE has concluded, based on a systems evaluation approach, that a substantial safety hazard does not exist for BWR plants.

However, in order to eliminate any concern for the continued long term coding of the core, GE has sent some recommended .

actions to BWR owners / operators via Service Information Letter No. 425.

f. Recualification Criteria for U.T. Personnel Representative of Engineering and Generic Connunications Branch, Division of Emergency Preparedness and Engineering Response was at EPRI NDE Center, Charlotte, NC to review requalification cri-teria for ultrasonic testing personnel in accordance with EPRI/

BWORG/NRC Coordination Plan.

g. Civil Penalties Paid On September 9, 1985 payment in the amount of $150,000 was received from TVA (Browns Ferry) for enforcement action (EA 85-51) relating to violations involving inoperable water level instrumentation,

h. Testimony Director, Division of Inspection Programs presented testimony before the Subcommittee on Health and Safety, Committee on Education and Labor, concerning radiation exposure at nuclear power plants on September 11, 1985.

i. ACRS Briefing Representatives of Division of Emergency Preparedness and Engineering Response and NRR briefed the Full ACRS on September 12, 1985 regard-ing recent significant operating events at nuclear power plants.

j. Quality Assurance (1) Representative of the Quality Assurance Branch, Division of Quality Assurance, Vendor, and Technical Training Programs, attended ASME Connittee on Nuclear Quality Assurance meetings in Knoxville, TN, September 11-13, 1985.

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ENCLOSURE D l SEP 131985 s n - - .e, .

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4 (2) Representatives of the Quality Assurance Branch visited the Millstone 3 nuclear power plant on September 12 and 13 to conduct an inspection of Millstone 3 Engineering Assurance Program and assurance program activities.

(3) The Chief, Quality Assurance Branch, met with representatives of Mitsubishi Heavy Industries on September 11 to discuss review of a forthcoming quality assurance topical report covering a spent fuel shipping and storage cask.

k. Vendor Program The following inspections were conducted this week by the Vendor Program Branch, Division of Quality Assurance, Vendor, and Technical Training Programs:

(1) Calvert Cliffs 1 & 2, Baltimore, MD--to review licensee's equipment qualification program implementation as required by 10 CFR 50.49. Inspection efforts will relate to Unit 2; followup to equipment qualification inspection of Unit 1 on October 15-19, 1984 will be performed.

(2) Rockbestos Company, New Haven, CT--to observe post-LOCA testing on radiation cross-linked polyethylene insulated Firewall III cable samples.

1. Operations Center A tour of the NRC Operations Center was conducted by a member of the Incident Response Branch on September 5, 1985 for the Directors of the Executive Borad of the Conference of Radiation Control and on September 9, 1985 for visitors from Britain. These tours dis-cussed the agency's incident response program.

m. Incident Response On September 11, 1985, the Chief and staff of the Incident Response Branch, Division of Emergency Preparedness and Engineering Response met with Region I mar gement to discuss the upcoming Relocation Tabletop Exercise (RTJ) and the Continuity of Government Program.

n. Emergency Preparedness (1) Representative of the Emergency Preparedness Branch, Division of Emergency Preparedness and Engineering Response participated in a combined emergency response facility appraisal at the Catawba and McGuire sites this week.

(2) Representative of the Emergency Preparedness Branch supported Region I in observing the full participation exercise at Pilgrim this week. ENCLOSURE D

OFFICE OF NUCLEAR REGULATORY RESEARCH Items of Interest Week Ending September 13, 1985 DOE Annual Workshop on Corrosion Research On September 5 and 6, the 00E Office of Energy Research held its annual workshop which reviews its corrosion research. The workshop took place at Sandia National Laboratory and involved groups doing corrosion research in many different parts of DOE, including those responsible for high level radioactive defense and civilian waste. The NRC was represented at the workshop by Dr. Michael McNeil, RES, at the invitation of DOE. Although these workshops encompass all aspects of DOE corrosion research, this year's workshop emphasized two areas of particular interest to the NRC's high level waste (HLW) licensing and research programs. The first area concerns the statistical nature of pitting corrosion initiation and pit growth, which is an important consideration in the models that the NRC will use in evaluating HLW metallic overpack performance. The work reported indicates steady progress in better understanding this form of corrosion and, more specifically, in being able to (1) account for macroscopic observations on the basis of an understanding of microscopic mechanisms, and (2) relate the statistical nature of pit initiation to deterministic chemical interaction models. The second area concerns the modeling and prediction of stress corrosion cracking, the other potentially significant cause of corrosion-induced HLW metallic overpack failure.

From reports at this workshop, it was clear that understanding of this process at the microscopic level is not well advanced and that it is likely that only phenomenological approaches, which do not deal with the fundamental mechanisms, will be usable in the NRC's assessment of stress corrosion cracking failures of HLW metal overpacks.

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i EMCLOSURE E )

SEP 131985

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I PISC-III Program at Ispra l

Italy MRC has joined the PISC-III (Progran for Inspection of Steel Components)

Program through our participation in the organizational meeting held on August 30 at the EEC (European Economic Consnunity) Research Center. Ispra.

Italy. The prior two PISC programs began in the late 1970s and early 1980s with the aim of evaluating the effectiveness of the ASME Code and European procedures for ultrasonic inspection of heavy plate and nozzle samples containing calibration-type side-drilled holes, fabrication and material flaws, and artificially produced cracks. The two programs have been very important in showing that " code minimum" inspection procedures are not adsguate to detect and size flaws in heavy steel plates or nozzles; never-th31ess, they have been useful for suggesting the capability of some ,

advanced methods for improved inspection reliability. The EEC has l urdirta!:en direct funding of the the PISC-III program, while at the same tiar) retaining the cooperation of the OECD-NEA for program management.

l PISC-III has the objective of establishing the reliability of current and advinced inspection techniques using realistic component-type specimens cenlaining real flaws or flaws which have been realistically emplaced witMn tha components. 1.arge plates, nozzle-bearing ring sections and even full-scale prcssure vessels are being employed in the program. RES was represented at the organizational meeting by Dr. J. Muscara, who was c1sted vice chairmen nf the Long-Term Planning Group. NRC is the driving for:c behind one of the PISC-III tasks titled "Round Robin Stainless Steel Reliability Studies," from which will come much experience of the reliability end accuracy of many different inspection methods on this

, setorial. Inspection of cast stainless steel is of great interest to NRC at this time because of limitations in reliability for detection and sizing of firys in this material which is extensively used in primary system Another task of interest early on the agenda l

piping in a number of PWRs.

is th test of flaw detection and characterization using the full-scale BWR i pretnro vessel at the MPA Stuttgart. The vessel, acquired because of a

! plant cincollation, has been implanted with numerous different type flaws so thct tests of the inservice inspection technology can be made under real'st'c pitnt conditions. The PISC-III program will run for at least thra.S y2ars and will include contributions and efforts from sost European

countries. The USA does not belong to the EEC which is bearing the cost of .

the PISC-III program; therefore, since we are not directly assessed, we will provide " contributions in-kind" of flawed test specimens. inspection results end data analyses. Participation in the management of P!SC-III is assured through our membership in the. OECD-NEA.

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l i ENCLOSURE E N 131$35

3-ASME Section XI Special Working Group on Plant Life Extension On August 26 Bill Morris of RES attended a meeting of the ASPE Section XI Special Working Group on Plant Life Extension which was established to develop ASME code modifications needed to support extended operation of nuclear power plant mechanical components. The working group also consists of representatives from several utilities, the NSSS vendors, architect engineers, and research organizations, including several national laboratories.

The initial activity of the working group will be to review the research being conducted by various organizations in support of life extension. Later the research findings will be factored into revisions of existing ASME codes or development of new codes.

Earthquake Data Meeting With French Earth shaking that might occur at a nuclear power plant site in the event of an earthquake is an important contributor to risk. The amount of shaking that the plant would undergo in an earthquake depends not only on the magnitude of the earthquake but also on the geologic structure in the vicinity of and underlying -

the plant. The kinds of rock and soil and their thickness and horizontal extent all are determining factors in the transmission of the earthquake's energy from its origin to the plant. Validation of the analytical models which are used to predict the effects of earthquakes is handicapped by the lack of field data concerning the transfer of earthquake energy through underlying geologic structures to the surface. Of particular importance is the seismic response of soil profiles typical of those which underlie nuclear power plants.

Mr. L. Beratan, Chief, Earth Sciences Branch of tnis Office is meeting with representatives of the French Government, their consultants and the University of California, Santa Barbara to discuss a potential research project designed to gather information on the transmission of earthquake energy through rock and a thick layer of soii. The project would be sponsored cooperatively by the NRC and the French Government and conducted by the University of California, Santa Barbara. It would utilize an existing deep borehole that has been drilled through alluvial soil ar.d chrystalline rock near Mamoth Lakes, California and two new holes that will be drilled into the crystalline rock beneath a deep .

soil layer at Anza, California, near the San Jacinto Fault. In this seismically active area, instruments will be installed at intervals down the borehole and on tne soil surface. These instruments will measure the acceleration and velocity resulting from seismic activity. The data. collected from this project would significantly improva the capability to analyze and predict the seismic response of nuclear power plants located on soil sites.

It would also provide data to address the validation of deconvolution models.

These models reduce recorded free-field accelerations by removing the effect of the soil column to obtain design accelerations for NPP's. Thus the uncer-tainty in this component of seismic risk assessment would be reduced by the use of validated models.

ENCLOSURE E SEP 131995

ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING SEPTEMBER 13, 1985 i

Foreign Visitors On Tuesday Dr. Roger Clarke and Mr. Geoff Webb, Secretary and Assistant Director for Operations, respectively, of the UK National Radiological Protection Board, met with representatives of RES, NMSS, NRR and IE to discuss (1) revisions to 10 CFR, Part 20, (2) De Minimis applications, (3) HLW and LLW regulations, and (4) radiological research efforts.

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,' ENCLOSURE G t

. SEP 131985

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. OFFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA ITEM OF INTEREST WEEK ENDING SEPTEMBER 13, 1985 AE0D Case Study Report, "0veraressurization of Emergency Core Cooling Systems in Boiling Water Reactors," AEOD/C502.

AE0D has finalized its case study of operating events involving an actual or potential overpressurization of a BWR emergency core cooling system. Eight events, each entailing the failure of a testable isolation check valve on the injection line of an emergency core cooling system, were identified and evaluated. Five of the eight events. involved an additional failure of the

• second and final isolation barrier--the inadvertent opening of a normally ~

closed motor-operated injection valve.

Each of these operational events is considered a precursor to an interfacing loss-of-coolant accident between the reactor coolant system and an emergency

core cooling system. Such an accident would involve the sudden discharge of reactor coolant at operating pressure and temperature outside the primary containment and would also likely disable one or more of the safety systems required to-mitigate the accident. Collectively, these operating events

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indicate a trend which has serious safety implications--that the likelihood of an interfacing loss-of-coolant accident is higher by two to eeveral orders of magnitude than had been previously assessed. This trend pi.vides a strong indication that prompt corrective actions should be taken to prevent a recurrence of these reported multiple failures. Several reccmmendations developed to eliminate the root causes of these occurrences have been forwarded to NRR for appropriate action.

i SEP 131985

REGION III STATUS REPORT DAVIS-BESSE LOSS OF FEEDWATER EVENT SEPTEMBER 13, 1985 Plant Status The plant remains in cold shutdown. Main condenser vacuum has been broken and the circulating water canal is being drained. Decay heat removal loop No. 1 is drained for maintenance.

SEF 131985 ENCLOSURE L

Nu EQUIPMENT STATUS (F0LLOWS TABLE 5.1 IN NUREG 1154)

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' EN TROUBLESHOOTING / ROOT CAUSE ITEM COMMENTS DETERMINATION ACTIVITIES RIII ACTIONS

1. Main Feedwater Turbine ** Cause determined to be component MFPs were tested on 09/05- Region III observed failure in speed control circuit. 06/85 with no problems noted. tests of MFPs and is Completed and report submitted to monitoring licensee NRR (08/16/85), evaluation of of reliability of the MFPs.

2. Closure of MSIVs** Cause determined to be that circuit Testing will continue through RIII monitoring was overly sensitive to momentary next week. Specialist from licensee's activities system perturbation. Report NRR will observe testing as and observing selected submitted to NRR (08/28/85). required, activities.

l Additional root cause determinations are continuing.

3. Steam Safeties, Atmos. Defective electronic module in Removal of eight MSSVs has RIII following Vents. ICS likely cause of problem with begun. The valves should be licensee activities.

atmosphere vent valves. Report shipped to Wylie the week of Vendor Programs Branch sent to NRR 08/25/85. MSSVs being 09/16/85 for testing. has been notified.

evaluated.

4. Aux. Feedwater Turbine Cause considered to be condensation Preparations are being made RIII inspectors to in long steam inlet lines. Report to modify the steam supply observe activities.

submitted to NRR 08/31/85. system. Governor from

1. 2AFWPT has been removed and sent to Woodward along with two spare governors for inspection and modifications.

5. AFW Containment Completed and report submitted Additional dp and flow RIII following Isolation Valves to NRR (08/19/85). Misadjustment testing is being evaluated, licensee's activities.

of bypass torque switch settings and inadequate testing procedure.

6. Steam Supply Valve ** Completed and reported submitted Activities completed. RIII to observe any

, to AFPT No. I to NRR 08/17/85. Additional testing additional testing.

n, is planned in hot Ei standby.

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• ITEM is COMMENTS DETERMINATION ACTIVITIES RIII ACTIONS m

7. Source Range NI Preliminary report issued Licensee is considering replacing RIII observing (08/30/85) the containment cable penetration activities.

modules.

8. PORY Completed and report sent to Valve will be rebuilt (as needed). RIII observing NRR (08/23/85). Root cause Two spare PORys will be rebuilt activitics.

not determined. Failed hydro at Crosby, and tested at Marshall Vendor Programs on 08/22/85 apparently due to Steam Station in Terrell, N.C'. Branch has been foreign material in valve. notified.

9.- S/U Feedwater Control ** Completed and report sent to Work complete. None.

Valve NRR (08/24/85). The valve functioned correctly during the June 9 event.

10. Recovery of AFP** Completed and report sent None. RIII to review operator Turbine to NRR (08/19/85). Training training program to deficiencies identified. assure proper operator actions.

11. AFP No. 1 Suction Revised report issued 09/09/85. Individual pump suction strainers RIII observing Root cause determined to Se will be removed and the common activities, Transfer excessive pressure drop across suction strainer will be common strainer caused by replaced with a coarser mesh transient flow variations. strainer.

12. Turbine Turning Gear *

13. Control Room HVAC*

14. Turbine Bypass Valve ** Completed and report sent to New drain header has been RIII to monitor.

NRR (08/17/85). Valve failure installed.

caused by water hammer.

• Status not maintained on this item since these type failures occurred pre-viously and do not appear to be unique to this event.

• • No change in status from previous update.

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4 Other Activities The new electric motor driven auxiliary feedwater pump is grouted in place.

Installation of pipe and valves is about 60% complete. Conduit installation, cable pulling and wire termination is in progress. The existing SUFP has been electrically disconnected.

Evaluations and inspections relating to the auxiliary feedwater system restraints are continuing. Baseline inspections of the No. 2 HPI and the No. 2 LPI systems are continuing. Nonconformance Reports (NCRs) have been written against 323 of the 342 pipe supports inspected so far. None of the NCRs have been dispositioned yet.

Testing of motor operated valves by M0 VATS, Inc. on the 51 valves that must be tested before the plant is taken to hot standby is completed. M0 VATS training and procedural development will be conducted next week and no valve tests are planned.

Corrective Action Plans Corrective action plans to repair equipment that malfunctioned during the event have been issued for the following equipment items. Item numbers correspond to Table 5.1 in NUREG 1154. .

ITEM DATE ISSUED

1. Main Feedwater Turbine 08/26/85

2. Closure of MSIVs 09/04/85

4. Auxiliary Feedwater Turbine 09/07/85

5. AFW Containment Isolation Valves 09/07/85 (Rev. 1) 6.. Steam Supply Valve to AFPT No. 1 08/29/85

8. PORY 09/09/85 (Rev. 2)

9. S/U Feedwater Control Valve 09/08/85 (Rev. 3)

10. Recovery of AFP Turbine 09/09/85

11. AFT No.1 Suction Transfer 09/04/85 4

14. Turbine Bypass Valve 09/05/85 (Rev. 2)

Davis-Besse Course of Action Report 09/09/85 Planned Meetings Commission briefing by NRR (Janes G. Keppler and staff to attend) -

September 17, 1985.

ENCLOSURE L SEP 131985 4

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Congressman Markey hearings - October 2, 1985.

Planned Special Inspections and Evaluations Maintenance Assessment Inspection (IE/RIII) - September 16, 1985

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4 TrainingAccreditationInspection(NRR/RIII)-September 24, 1985 i

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• Annual INPO Evaluation - September 30-October 11, 1985.

Miscellaneous Ottawa County Commissioners requested a briefing on the June 9, 1985 event.

Region III is in the process of scheduling the meeting.

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4 ENCLOSURE L SEP 1- 31985 5

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ca 05 ' NRR MEETING NOTICES

• EE SEPTEMBER 13, 1985 DOCKET APPLICANT /

DATE/IIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 9/16/85 50-390/391/ P-118 To discuss Qualification of TVA C. Stahle

'9:00 am 327/328/438/ Bethesda, Md. Equipment at TVA Plants (Bellefonte, Browns ,

439/259/260/ Ferry, Sequoyah and 296 Watts Bar) 9/16/85 50-278 P-114 To discuss core spray sparger Philadelphia Elec. Co. G. Gears 9:00 am Bethesda cracks and repairs at Peach Bottom 3 ,

9/17/85 50-445 P-118 To discuss visual inspection Texas Utilities A. Vietti-Cook 9:00 am 50-446 Bethesda of painted support welds and design issues related to active valves.at Comanche Peak 9/18/85 50-219 GPU Nuclear To review status of licensing GPU Nuclear J. Donohew 9:00 am Parsippany, NJ actions for Oyster Creek 9/20/85 50-219 P-114 To discuss status of Expanded GPU Nuclear J. Donohew 9:30 am Bethesda Safety System Facility planned by the licensee for Dyster Creek 9/24-26/85 50-443 Seabrook Site To inspect completion of Power Public Serv. Co. of V. Nerses 50-444 Seabrook, NH System Branch confirmatory New Hampshire '*^

items

• Copies of summaries of these meetings will be made publicly available and placed in the respective docket file (s) in the NRC and local public document rooms E

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$ NRR MEETING NOTICES

• DOCKET APPLICANT /

DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 9/25/85 50-413 Catawba Site To audit Catawba Inadequate Duke Power Co. K. Jabbour 10:00 am 50-414 Clover, SC Core Cooling Instrumentation ORNL for Implementation Review Copics of summaries of these meetings will be made publicly available and placed in the respective docket file (s) in the NRC and local public document rooms.

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NHSS MCETING NOTICES m .

FOR WEEK ENDING: 9/13/85 l

-o Division cf Fuel Cycle and Material Sarcty -

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m DOCKET ATTENDEES /

LOCATION PURPOSE APPLICANT NRC CONTACT g DATE/ TIE NUMBER ,

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9/16-17/85 Hyatt Regency ANSI N14 Comittee Meeting N14 Committee Mbrs. MacDonald Ilotel (Capitol " Packaging and Transportation A. Grella (IE) f R'

11111) D.C. of Radioactive Materials." D. Ilopkins (RES)

C. MacDonald (FC) 9/17/85 Uillste Exchange of information on uranium Messrs. Chalabreysse Cool ,

9:00 am exposures and uranium ha.ndling. & Camarasa (Service d'Ilygiene Industrielle, CEA, France)

Reps of RES and HMSS j

9/18/85 Edison Electric Utility Companies' Reps of DOT, DOE MacDonald i 1:30-4:30 pm Electric Nuclear Transportation Group & Electric Utilities Inst. Meeting. C. MacDonald (FC)

I (D.C.)

9/18/85 Willste To discuss source.and device L. lienerson and Miller f

i licensing issues with Amercham M. Shilton (Amersham)

Corporation. Reps of NMSS 9/19/85 Willste New pellet shipping container. Reps fm Babcock Odegaarden l 9:00-11:00 am & Wilcox R. Odegaarden (FC) ,

B. Lake (FC) j

11. Lee (FC) .

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cs DIVISION OF WASTE MANAGEMENT 9/12/85 ll 1

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DOCKET ATTENDEES /

DATE/ TIME NUMBER LOCATION PURPOSE APPLICATION NRC CONTACT  !

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't 9-26-27 Willste Bldg. Rs. 106 Performance Allocation SCoplan SCoplan l 9/26 9:00 - 5:00 p Silver Spring, MD Discuss role, timing and WM staff PBrooks

! 9/27 9:00 - 12 noon approaches to performance DOE staff  ;

allocation DOE contractors  :

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NONE

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V RES MEETING NOTICES Seotenber 13. 1985

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PURPOSE APPLICANT NRC CONTACT g DATE/ TIME NUMBER LOCATION 1133-S5 Safeguards Workshop Safeguards Ting 9/26/a5 Section,RES 9:00-5:00 C2 h

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-n OSP MEETING NOTICES September 13, 1985 1

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rit E DATE/ TIME' LOCATION PURPOSE ATTENDEES NRC CONTACT 9/23/85 Lake Buena Attend and speak at American Financial officers JSaltzman

! 1:30PM Vista, Fla. Public Power Assoc. (APPA) of public utilities Accounting, Finance & and accounting firms Information Systems Workshop -

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. cs RII MEETING NOTICE DOCKET ATTENDEES /

NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT DATE/ TIME RII Office SALP Board Meeting - Selected RII and Walker ,

09/17/85 8:30 am Hatch & Vogtle facilities NRR staff members 09/18/85 RII Office Enforcement Conference - Licensee and Selected Stohr 10:00 am Babcock & Wilcox Company's ' RII Staff Members '

Naval Nuclear Fuel Division 09/19-20/85 Chattanooga, Region II Management Region II Senior Grace Tennessee Meeting Managers 4

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