ML20133G028

Weekly Info Rept for Wk Ending 851004

ML20133G028
Person / Time
Issue date:	10/09/1985
From:	Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To:
References
WIR-851004, NUDOCS 8510150131
Download: ML20133G028 (51)

Text

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• pg October 9,1985 For: The Comissioners F,gm: T. A. Rehm, Assistant for Operations, Office of the EDO

Subject:

WEEKLY INFORMATION REPORT - WEEK ENDING OCTOBER 4, 1985 A summary of key events is included as a convenience to those Comissioners who may prefer a condensed version of this report.

Contents Enclosure Administration A Nuclear Reactor Regulation B Nuclear Material Safety and Safeguards C Inspection and Enforcement D Nuclear Regulatory Research E Executive Legal Director F*

International Programs G State Programs H Resource Management I Analysis and Evaluation of Operational Data J*

Small & Disadvantaged Business Utilization & Civil Rights K*

Regional Offices L CRGR Monthly Report M*

i Executive Director for Operations N*

Items Addressed by the Commission 0 Meeting Notices P

Proprietary or Other Sensitive Information (Not for Q external distribution)

• No input this week.

lT. A. Rehm,0 Y

• ta t To'r Operations Office of the Executive Director

! for Operations

Contact:

T. A. Rehm, ED0 492-7781 holgg ony WEEKLYINFOREPT PDR

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i HIGHLIGHTS OF WEEKLY INFORMATION REPORT WEEK ENDING OCTOBER 4, 1985 i i Davis-Besse Nuclear Power Station, Unit 1 i

At our request, the ACRS has scheduled a review of the corrective

! action program which must be completed prior to restart of Davis-Besse

! (following the June 9 loss of feedwater event). An ACRS Subcomittee

chaired by F. Remick toured the facility during the morning of -

October 4, 1985. The Subcomittee also held a public meeting with Toledo Edison and the NRC staff at Oak Harbor Ohio the afternoon of October 4. On October 10, 1985, presentation will be made by Toledo Edison and the staff to the full-Comittee. The need for additional meetings will be assessed at the conclusion of the full-Comittee. The '

i staff plans to also discuss the short-term and long-term generic safety i issues which it has initiated as the result of its investigation of this event.

Millstone 3 On October 2, 1985 the staff met with John O of Northeast Nuclear Energy Company (NNECO) to discusspeka, Senior a number Vice President of key l open issues requiring resolution prior to licensing. With regard to STA and Hot Operating Experience, the Director Division of Human i Factors Safety explained the Comission's position regarding STA as

' presented in SECY-85-150: Final Policy Statement on Engineering Expertise on Shift; and Hot Operating Experience as presented in the j NTOL Comission Brief held on September 3,1985.

It was stated that two shifts do not meet the Comission's requirements regarding STA dual role because Comission Policy does not permit 4 individuals without an engineering or science degree to fill the dual j role. Two other shifts do not meet the Comission's requirements

regarding hot operating experience because Comission policy does not i permit individuals with BWR hot operating experience to satisfy this requirement for a PWR. Several alternatives for satisfying these requirements were discussed with NNECO including four shift rotation and shift augmentation by experienced personnel from other reactors or i engineering staff. The applicant is reviewing its ability to satisfy i alternative proposals that meet the Comission's position, or request

! the staff to present the current position to the Comission for their approval.

Dakota low-Level Radioactive Waste Compact The South Dakota Suoreme Court has upheld the constitutionality of a State law that requires voters to approve the State's entry into an Interstate 4

compact for low-level radioactive waste. The Court added that the decision of the voters is binding on the State. A special election to consider a

compact with North Dakota is scheduled for November 12, 1985.

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OCT 4 1985

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OFFICE OF ADMINISTRATION 1

Week Ending October 4, 1985

, ADMINISTRATION OF THE FREEDOM 0F INFORMATION ACT

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STATUS OF REQUESTS Initial Appeal of Recuest Initial Decision Carryovers, 1984 179 23 Received, 1985 674 40 Granted 539 27 Denied 152 16 Pending 162 20 -

, ACTIONS THIS WEEK Received James T. Lawless, Requests copies of the Deviation Analysis Reports for The Plain Dealer the Perry nuclear power plant.

(85-658)

Randy Wenner, Requests a copy of NRC Investigation Report I-84-014 WTVH Television concerning the Nine Mile Point nuclear power plant.

(85-659)

Louise Ponce Requests records relating to the manufacture or storage (85-660) of radioactive materials in Maywood, New Jersey, including records relating to Maywood Chemical Company and Stephan Chemical Company.

Dinah Wisenberg, Requests copies of correspondence between the Commission McGraw-Hill and Rep. Edward Markey since June 1984 regarding 01 and Publications 01A investigations related to the Grand Gulf nuclear Company power plant and any reports associated with those (85-661) investigations.

Dinah Wisenberg, Requests records of all meetings in the last year between McGraw-Hill representatives of the Nuclear Utility Management and Publications Human Resources Committee and the NRC Comissioners.

Company (85-662)

Margaret L. Ryan, Requests all records generated by the NRC and the utility McGraw-Hill in meetings held during the past year aimed at developing 1 Publications integrated "living" schedules for Turkey Point Units 3 Company and 4.

(85-663)

CONTACT: J. M. Felton 492-7211 ENCLOSURE A OCT 4 1985

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Received, Cont'd Margaret L. Ryan, Requests a copy of the report of the OIA audit of 01 McGraw-Hill which was forwarded to the Commission on May 15, 1985.

Publications Company (85-664)

Edward A. Firestone, Requests five categories of AEC and NRC records from General Electric 1955 to the present, which are not already in the PDR, Company regarding pressure suppression containments associated (85-665) with BWRs.

Kathryn H. Urban, Requests information submitted by specified manufacturers Cintichem, Inc. and users of sealed sources for the " Registry of (85-666) Radioactive Sealed Sources and Safety Evaluation of Sources."

(NRC employee) Requests three categories of records concerning herself.

(85-667) 4 Steven C. Sholly, Requests summaries and evaluations of LERs from fuel MHB Technical loading to declaration of commercial operations for Associates seven specified units.

(85-668)

Steven C. Sholly, Requests three categories of records regarding the recent MHB Technical visit of the Caseload Forecast Panel to Seabrook Unit 1.

Associates (85-669)

Cynthia Hale Requests three categories of records related to the (85-670) Clinton nuclear power plant and her lawsuit, Cynthia Hale

v. Baldwin Associates.

Michael K. O'Mealia, Requests a copy of SECY-85-56A.

Doc-Search Associates (85-671)

James Craig Dodd, Requests all records relating to operations conducted

Dodd & Helm pursuant to an agreement between DOE and Sandia (85-672) Corporation and two other specified agreements regarding a " Western Gas Sands Multi-Well Experiment," conducted in Garfield County, Colerado.

Billie P. Garde, Requests all records related to inspection report 85-02 Government dated September 11, 1985, regarding the Comanche Peak Accountability nuclear power plant.

Project (85-673) l i

(NRCemployee) Requests a copy of his performance appraisal for the (85-674) rating period of October 1983 through September 1984.

ENCLOSURE A OCT 41985

3 Received, Cont'd Mozart G. Ratner, APPEAL TO THE COMMISSION for the release of one denied Attorney-At-Law record regarding a request for all memoranda and notes (85-A-40-85-542) of all conferences and conversations on which the letter dated July 19, 1985, to Mr. Ratner from Mr. Jensen of the Office of the General Counsel was based.-

Granted Billie P. Garde, In response to a request for copies of all records Government regarding IE Information Notice No. 85-40, " Deficiencies Accountability in Equipment Qualification Testing and Certification Project Process," made available three records. Informed the (85-454) requester that additional records subject to this request are already available at the PDR.

Richard L. Jacobs, In response to a request for all records provided Washington Document to and received from any Congressional member, committee, Service or subcommittees regarding any pending or completed (85-478) escalated enforcement action commenced against any power reactor licensee or applicant since January 1,1984, made available 66 records. Informed the requester that additional records subject to this request are already available at the PDR.

Hal B. Tucker, In response to a request for certain records relating to Duke Power Company qualifications of Senior Reactor Operators for 19 listed (85-610) units, made available copies of 191 abstracted records

! subject to this request.

(NRC employee) In response to a request for the current grade levels of 2

(85-656) secretaries in five specified offices, made available the requested information.

. (NRC employee) In response to a request for a copy of his performance (85-674) appraisal for the rating period of October 1983 through September 1984, made available a copy of the requested appraisal.

4 Denied Steve Kohn, In response to a request for various categories of Richard Condit, records relating to Dow Chemical Company of Midland, Government Michigan, made available 409 records. Denied portions Accountability of 24 records, release of which would constitute a Protect clearly unwarranted invasion of personal privacy.

(85-259) Denied portions of 13 records which identify procedures 4

for safeguarding licensed special nuclear material at a licensed facility or plant. Informed the requester that additional records subject to this request are already available at the PDR.

ENCLOSURE A OCT 4 1985

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4 Denied, Cont'd Joseph L. Swiger, In response to a request for records regarding the Envirocare, Inc. International Nutronics Facility in Dover, New Jersey, (85-317) for the period January 15, 1985, through May 7, 1985, made available 30 records. Infonned the requester that additional records subject to this request are already available at the PDR. Denied portions of one record containing confidential business-(proprietary) information.

Thomas Devine, In response to a request for all records regarding the Government Office of Inspector and Auditor inquiry into charges that Accountability NRC staff responded improperly to allegations by whistle-Project blowers at the Diablo Canyon nuclear power plant, denied (85-589) these records in their entirety because they are predecisional in nature and pertain to an ongoing investigation.

Michael S. Terpilak, In response to a request for four categories of records i Nucleon Lectern pertaining to the byproduct material license issued to J

Associates, Inc. Alaron Corporation, made available 11 records. Denied (85-616) portions of two records, disclosure of which would constitute a clearly unwarranted invasion of personal privacy.

Jesse R. Meer, In response to a request for copies of letters to and Bishop, Liberman from Mr. Beavers regarding shutdown of the Salem and

& Cook Hope Creek nuclear power plants, made available two (85-645) records. Denied portions of one record, disclosure of which would constitute a clearly unwarranted invesion of

] personal privacy.

Donald L. Schlemer, In response to an APPEAL TO THE E00 for the release of Government an undated Final Safety Analysis Report on the Philippine Accountability Nuclear Power Plant - 1, continued to deny this report Project because it contains information received in confidence (85-A-35-84-559) from a foreign source.  ;

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ENCLOSURE A

OCT 419o5

3 WEEKLY INFORMATION REPORT DIVISION OF CONTRACTS WEEK ENDING OCTOBER 4, 1985 RFP ISSUED RFP No.: RS-RES-86-104

Title:

" Cooperative Human Reliability Evaluation Program"

Description:

The primary objective of this 12-month research program is to compare and contrast Nuclear Regulatory Commission and Electric Power Research Institute analytic tools for conducting human reliability analysis with those of other participating nations to derive conclusions from the comparison that can be used to assess the current state-of-the-art and to guide future research. This objective will be accomplished by (1) selecting in conjunction with other nations participating in the

" benchmark" study, a set of precursor / accident sequences for analysis, (2) identifying a set of tools and data appropriate for analyzing those sequences, and (3) conducting human reliability analyses of those sequences and collect data on the utility of the attendant analytic tools.

Period of Performance: 1 year Sponsor: Office of Nuclear Regulatory Research Status: RFP issued on September 30, 1985. Proposals due October 30, 1985.

PROPOSAL UNDER EVALUATION RFP No.: RS-01E-85-156

Title:

" Technical Assistance in Developing and Implementing Programs and Procedures for Reactors Requiring Special Inspection Resources"

Description:

The objective of this project is to provide technical assis-tance to the NRC for activities pertaining to problem reactors during construction and operation, including development of an NRC program that standardizes inspection procedures for significant problem areas and emergency outages, and assisting in inspections.

Period of Performance: 3 years Sponsor: Office of Inspection and Enforcement Status: RFP closed on September 24, 1985. Proposals forwarded to Source Evaluators for review on September 27, 1985.

CONTRACT AWARDED i

RFP No.: RS-NMS-85-009

Title:

" Technical Assistance in Hydrogeology - Project 8 - Analyses"

Description:

The contractor shall provide technical assistance to the NRC in its review of DOE site investigations for a potential High Level Waste (HLW) geologic repository.

Period of Performance: 2 years with 3 one-year options Sponsor: Office of Nuclear Material Safety and Safeguards Status: Cost-Plus-Fixed-Fee type contract awarded to Nuclear Waste Censultants in the amount of $1,025,800.00 effective September 27, 1985. ENCLOSURE A OCT 4 1985

i 0FFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending October 4, 1985 -

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, River Bend Station On September 24, 1985. Gulf States Utilities (GSU) requested an emergency license amendment to modify a surveillance requirement in the Technical Specifications. The Technical Specifications required that

the transient voltage during full load rejecticn testing of the HPCS diesel generator not exceed 115% of the rated steady state voltage.

, Baseline testing conducted during the middle of September convinced the utility that the 115% limit was too low. On September 26, 1985, the staff granted GSUs request for a maximum transient voltage level of 130% of steady state as an emergency license amendment.

Initial criticality is now estimated by the utility to occur during the weekend of October 5/6, 1985.

Pilgrim Nuclear Power Station By letter to Chairman Palladino dated September 23, 1985, Boston Edison Company (BECo) requested an extension beyond November 30, 1985 to complete environmental qualification of five types of electrical 4

components, consisting of 15 individual items. All of these items are scheduled for completion of testing by November 30, 1985; however, the

, extension request was submitted prior to September 30, as required by 4 Generic Letter 85-15, since BECo cannot guarantee that the testing will be completed by November 30 or that all test results will be positive.

Grand Gulf, Unit 1 The Mississippi Public Service Commission issued an order directing 4

suspension of construction of Grand Gulf Unit 2. The order stated that i the reliability of the Mississi l South Energy, Inc. (companies) cost ppi Power and estimates Light Company for completion and Middle of Grand Gulf Unit 2, as well as the companies' ability to economically justify the need for power and continued construction and completion of Unit 2 are in serious question. The order also requires the companies to report to the Public Service Commission before the end of the year i regarding their future plans for Unit 2.

, Mississippi Power and Light Company has performed only a limited amount

! of construction on Unit 2 over the past few years to conserve financial i' resources. In compliance with the order, these limited construction activities will be suspended. ,

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ENCLOSURE B OCT 41985

Davis-Besse Nuclear Power Station, Unit 1 At our request, the ACRS has scheduled a review of the corrective action program which must be completed prior to restart of Davis-Besse (following the June 9 loss of feedwater event). An ACRS Subcomittee chaired by F. Remick will tour the facility during the morning of October 4, 1985. The Subcomittee will hold a public meeting with Toledo Edison and the NRC staff at Oak Harbor, Ohio the afternoon of i

October 4. On October 10, 1985, presentation will be made by Toledo Edison and the staff to the full-Committee. The need for additional meetings will be assessed at the conclusion of the full-Comittee. The staff plans to also discuss the short-term and long-term generic safety issues which it has initiated as the result of its investigation of this event.

, Shoreham Shoreham weathered the passage of Hurricane Gloria across Long Island with no damage. The plant remained in cold shutdown during the entire i

event. The maximum wind speeds in the area exceeded 100 mph at Brookhaven National Lab, to the south, but water levels at the intake structure remained 15 feet below the design maximum. The only problem which occurred was the loss of one of the two sources of offsite power from the 69KV grid. The 20MW gas turbine on site started automatically to restore the 69KV feeder. All low-power testing has been suspended indefinitely while LILCo employees from Shoreham are assisting with the restoration of power elsewhere on Long Island.

Peach Bottom Atomic Power Station, Units 2 and 3 Earlier this month, Philadelphia Electric Company's (PECo) licensing staff indicated that they were considering the submittal of a request to operate beyond November 30, 1985 with unqualified electrical i equipment installed at both Peach Bottom units. PECo indicated that their consideration of this action was based upon the NRC staff's recent guidance on EQ deadlines (Generic Letter 85-15). The NRC staff again contacted the licensee on September 2C and 26, 1985 to verify their intentions to request an extension ir. accordance with GL 85-15.

The licensee has on September 27 indicateo that it now believes that both Peach Bottom units will be in compliance with 10 CFR 50.49 after November 30, 1985 and, therefore, they do not plan to submit an extension request as per GL 85-15 guidance.

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l i ENCLOSURE B OCT 4 1985

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Haddam Neck Plant and Millstone Unit 1 By letter to Chairman Palladino dated September 30, 1965, Connecticut t

Yankee Atomic Power Company (CYAPCo) and Northeast Nuclear Energy Company (NNECo) requested extensions beyond November 30, 1985 to complete environmental qualification at the Haddam Neck Plant and i Millstone Unit 1 respectively. '

i CYAPCo requested an extension for 14 valve motor operators and 20  ;

reactor coolant loop resistance temperature detectors until its next  ;

outage which is scheduled to begin on January 4, 1985. All the '

equipment identified above will be replaced with qualified components i 4

during this outage.

NNECo requested an extension for a total of 17 valve motore operators at Millstone Unit 1. The qualification requirements for 11 valve motor operators is proposed to be evaluated under the ISAP effort. NNECo 4 also requested a permanent exemption from 10 CFR 50.49 for 6 valve

, motor operators. NNEco (Millstone 1) plans to replace an additional 11 valve motor operators in their next cutage, which begins in late i October 1985.

, Rancho Seco Nuclear Generating Station l

On September 29, 1985, the Rancho Seco station started returning to power following a refueling outage which began March 15, 1985. Prior to heatup, the utility repaired the high point vent leak and installed the missing pipe supports, completed walkdown of the safet/ systems supports dispositing all non-conformances found. The ut' oty has implemented a program in response to an INPO inspection to (1) ensure a more active involvement by supervisory personnel within the plant to ensure that policies and procedures are implemented and adhered to, (2) j more closely control maintenance activities in such a manner to ensure that the control room is aware of activities in progress and (3) i upgrade the watch standing performance of non-licensed operators within j the plant.

As part of the refueling outage, the licensee inspected the steam generators and plugged some tubes, modified the HVAC system in the control room and the Tech Support Center (NUREG-0737 item), completed the major portion of the 10 CFR 50 Appendix R modifications, replaced l

the main feedwater flow nozzles, completed the operational EQ program, did diesel generator maintenance work, completed the Tech Support Center, implemented the ATOG procedures and made SPDS operational.

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ENCLOSURE B

, OCT 4 1985

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I Rancho Seco Nuclear Generating Station On October 2, 1985, the Rancho Seco reactor tripped on high reactor coolant pressure. The plant had been operating at 40% power for about 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> when reactor power was reduced to 15% to perform a turbine overspeed trip test. For unknown reasons, a main vacuum loss occurred which resulted in a turbine trip. Since reactor power was less than 15%, reactor trip did not occur. For unknown reasons, the main feedpumps tripped; and the reactor tripped on high primary system pressure. Auxiliary feedwater started as per design, however the automatic steam control valve to the 4A feedwater heater apparently failed open and caused excessive steam drain from the steam gengrators. Thegteamdraincausedrapidprimarysystemcooldownfrom 582 F Tave to 490 F Tave. High pressure injection pumps were manually initiated and operated for 10 minutes to restore pressurizer level.

Pressurizer level decrease from 220 inches to 35 inches. Steam to the faulty feedwater heater was secured and the cooldown transient stopped.

The licensee does not plan to restart the plant until the cause of the equipment failures is determined. The licensee has requested help from B&W to evaluate whether the cooldown rate remained within design limits.

ENROSURE B OCT 4 1905 l

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1 D.C. Cook 1 The D.C. Cook Unit No. 1 is currently shutdown for the 10 years ISI.

The licensee has notified NRR of an input error in the T00DEE 2 -

computer coce by Exxon Nuclear Fuels which if corrected withoutg further changes, weald cause the analyzed peak clad temperature of 2200 F to be exceeded. The licensee is expected to submit a request to adjust the analysis of record to account for conservatisms in the stored energy.

Adjustmentinthestoredgnergywouldreducetheanalyzedpeakclad temperature to below 2200 F without the need to reduce power or make changes to peaking factors or setpoints. The Unit 1 plans to startup to week of October 7, 1985. The Unit 2 is not affected by the error.

D.C. Cook 2 On September 30, 1985, the Indiana and Michigan Electric Company submitted a request to the Comission to extend the deadline for environmental qualification of equipment. The requested deadline is the end of the current fuel cycle but no later than February 28, 1986.

The extension is necessary because to three unplanned outages due to steam generator leakage. Unit 2 had been granted an extension until November 30, 1985 for some of the items. The remainder of the items were recently discovered; all are located inside containment and require plant shutdown to complete. The licensee completed some qualifications activities during the steam generator leakage outages.

Millstone 3 On October 2, 1985 the staff met with John O of Northeast Nuclear Energy Company (NNECO) peka,a Senior to discuss numberVice President of key open issues requiring resolution prior to licensing. With regard to STA and Hot Operating Experience, the Director, Division of Human Factors Safety explained the Commission's position regarding STA as presented in SECY-85-150: Final Policy Statement on Engineering Expertise on Shift; and Hot Operating Experience as presented in the NTOL Commission Brief held on September 3, 1985.

It was stated that two shifts do not meet the Commission's requirements regarding STA dual role because Comission Policy does not permit individuals without an engineering or science degree to fill the dual role. Two other shifts do not meet the Commission's requirements regarding hot operating experience because Commission policy does not permit individuals with BWR hot operating experience to satisfy this requirement for a PWR. Several alternatives for satisfying these requirements were discussed with NNECO including four shift rotation and shift augmentation by experienced personnel from other reactors or engineering staff. The applicant is reviewing its ability to satisfy alternative proposals that meet the Commission's position, er request the staff to present the current position to the Comission for their approval.

ENCLOSURE B OCT 4 1985

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A H. B. Robinson H. B. Robinson, Unit 2 initiated a power reduction to 91.5% of rated-(approximately 2100 MWt, 666Mwe, net) September 28, 1985 about midnight. The de-rate was required due to an error found in the T00DEE2 computer analysis by Exxon Nuclear Fuels. Tgecurrentpower level will maintain peak clad temperature below 2200 F under accident conditions. It has also been necessary to administratively reduce F (HotChannelFactor)toamaximumof2.13fromthecurrentlimit2.33.

The OP delta T and OT delta T setpoints have been reduced consistent with the de-rate.

The situation arises from an inadvertent omission of the decay heat produced in an incremental radial element in the computer model; the limitation is encountered in the large-break LOCA portion only of the K(z) curve. Carolina Power and Light Company has a license amendment penaing for this curve. A Part 21 report has been initiated by Exxon with Region V.

Restart of Three Mile Island, Unit 1 (TMI-1)

On October 2, 1985, the U.S. Supreme Court vacated the previously imposed judicial stay on the effectiveness of the Commission Order 4

authorizing restart of TMI-1. The Director, NRR, issued a letter to the licensee of Three Mile Island, Unit 1, authorizing operation of the plant.

The licensee is conducting startup in accordance with a staff approved power ascension schedule. This schedule has selected " hold" points where the licensee must receive verbal permission from the Regional Administrator before proceeding. The power ascension schedule covers approximately a 90 day period. Deborating started at 5:50 a.m. on October 3 and the 1% shutdown margin was reached around mid-morning.

The Regional Administrator released the licensee from the first hold point at 10:15 a.m., and the plant is being brought to criticality.

Criticality should occur between 2 and 3 p.m. on October 3.

Region 1 commenced enhanced inspection coverage of restart at 4:00 a.m.

on October 3 and the planned support from other Regions and from

contractors will be forthcoming in the next day or two.

On October 2, there was a demonstration at the plant entrance. It was non-violent but with some arrests for civil disobedience. There has been no subsequent activity outside the plant as of 9:00 a.m. on October 3.

1 Governor Thornburg of Pennsylvania issued a supportive statement that it is time to cooperate and assure that the plant operates safely.

ENCLOSURE B OCT 419c5

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. A Arkansas Nuclear One, Unit No. 1 (ANO-1)

ANO-1 was manually tripped at 6:30 a.m., Tuesday, October 1, 1985, -

because a Main Steam Line Isolation Valve (MSIV) inadvertently closed.

The licensee believes that the inadvertent closure of the MSIV could be caused by a short in the circuit which controlled the operation of the MSIV. The licensee is investigating the matter and taking corrective actions. While shutdown the licensee is also repairing a malfunction in the indication circuitry of a control rod drive. They expect to be back to operation on Wednesday, October 3, 1985.

Fort St. Vrain Public Service Company of Colorado (PSC) has requested a schedule extension for the Fort St. Vrain (FSV) Nuclear Generating Station under the provisions of 10 CFR 50.49(g). PSC's request is to extend the schedule for compliance with 10 CFR 50.49 for all safety related equipment at FSV except the PCRV linder cooling system until March 31, 1986. The schedule extension was requested because a number of activities need to be completed to achieve full qualification. These i include aging and operability time studies, field walkdowns, I

installation of the Steam Line Rupture Detection / Isolation System, reevaluation of the accident temperature profiles, and update of the qualification files. The licensee's submittal dated September 24, 1985

(P-85334) discusses FSV's exceptional circumstances, provides justification for continued operation, and discusses the necessity for the schedule extension.  :

The licensee states the unique features of the FSV gas cooled reactor are not fully recognized by 10 CFR 50.49. In addition, FSV did not receive a Technical Evaluation Report or a Safety Evaluation Report from the staff. The licensee states that such reviews would have been of assistance in identifying qualification problems.

, In the interim, the licensee stated that continued operation of FSV was justified. The new Steam Line Rupture Detection / Isolation System to be

installed before November 30, 1985 would assure that the liner cooling system would remain operable. The LCS would be fully qualified under 10 CFR 50.49.

The staff evaluation of this unique, virtually across the board equipment qualification extension is ongoing. A Comission paper is

being prepared and is expected to be complete by November 6, 1985.

l ENCLOSURE B OCT 41985 i

, JL NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT WEEK ENDING OCTOBER 4,1985

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 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). The defueling platform is

installed over the Internal Indexing Fixture in preparation for defueling.

- Calculated reactor decay heat is less than 12 kilowatts.

- RCS cooling is by natural heat loss to the reactor building ambient atmosphere. Incore thermocouple readings range from 70*F to 91*F i

with an average of 79*F. Average cold leg temperature will no longer be reported.

The average reactor building temperature is 56*F. The reactor i building airborne activity is 4.8 E-9 uCi/cc Tritium and 1.5 E-10 uCi/cc particulate, predominantly Cesium 137.

l 2. WASTE MANAGEMENT

- TheSubmergedDemineralizerSysten(SDS)commencedprocessingbatch 124 from neutralizer tanks (WDL-T-8 A/B) to SDS monitor tanks (SDS-T-1 A/B). To date 3,036 gallons from this batch have been processed.

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! ENCLOSURE B l OCT 4 1985

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e A 2

- EPICOR II comenced processing batch 267 from CC-T-1 to CC-T-2. To date 18,296 gallons from this batch have been processed.

- Total volume processed through SDS to date is 2,681,278 gallons, and the total volume processed through EPICOR II is 2,966,411 gallpns.

3. DOSE REDUCTION /DEC0f4TAMINATION ACTIVITIES

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

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

4. STRONTIUM-90 INSPECTION

- A special inspection was conducted on September 30 through October 2,1985 to review the licensee's report that due to misinterpretation of a calibration procedure, the Strontium-90 (Sr-90) activities reported for some solid waste shipments were one-half the actual activities. The inspectors also reviewed the licensee's efforts to detarmine the extent of the corrections which may be needed. The licensee agreed to perform an independent assessment of the chemistry Quality Assurance / Quality Control (QA/QC) program; implement a formalized QA/QC program; and to assure that all procedures used at TMI-2 for Sr-90 analyses are clear and accurate.

5. ENVIRONMEf4TAL MONITORIfiG US Environmental Protection Agency (EPA) sample analysis results show TMI site liquid effluents to be in accordance with regulatory limits, NRC requirements, and the City of Lancaster Agreement.

TMI water samples taken by EPA at the plant discharge to the river consisted of seven daily composite samples taken from September 14 through September 21, 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 September 15 through September 21, 1985. A gamma scan detected no reactor related radioactivity.

The NRC outdoor airborne particulate sampler at the TMI Site collected a sample between September 25 and October 2,1985. No reactor related radioactivity was detected. Analysis showed Iodine-131 and Cesium-137 concentrations to be less than the lower limits of detectability.

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ENCLOSURE B OCT 41985

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REACTOR BUILDING ACTIVITIES *i

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

- Work is in progress on the canister positioning system and canister

! handling bridge.

Installation of the vacuum defueling system is in progress.

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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.

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All four of the fuel canister storage racks have been inspected.

Three of the four fuel canister storage racks have been positioned in the spent fuel pool "A" and their position is being adjusted.

] The fourth rack has been installed into the fuel pool.

'8. NRC EVALUATIONS IN PROGRESS Technical Specification Change Requests numbers 48 and 50.

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

i - Fuel Canister Technical Evaluation, Revision 1.

- Defueling Safety Evaluation.

- Application for seismic exemption.

- SDS Technical Evaluation and System Description Update.

j - Core Stratification Sample Safety Evaluation.

- Heavy Load Handling Safety Evaluation Report.

i - Boron Dilution Hazard Report Defueling Water Cleanup System Technical Evaluation Report, Revision i 7.

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NRC Vendors Program Branch has completed an inspection at Joseph Oat Corporation which is fabricating fuel canisters. A report of the j ,

inspection findings will be issued in a few weeks.

9. PUBLIC MEETING 1 The next meeting of the Advisory Panel is scheduled for October 16, 1985 i in Lancaster, Pennsylvania at 7:00 PM. The meeting will be held in the i Lancaster Council Chambers at 201 North Duke Street. Dr. H. Arnold j

Muller, Secretary, Department of Health will review the results of the Health Department's recently completed epidemiology studies.

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. ENCLOSURE B i OCT 4 1985 1

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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.

h ENCLOSURE B OCT 41985 l

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OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending October 4, 1985 i

j Near-Term NRC Actions Under the NWPA Section: 134 of NWPA: Final Rule on Hybrid Hearings Action: The Commission voted to approve the final rule establishing procedures for expansion of onsite spent fuel storage capacity or transshipment of fuel on September 5, 1985. -

Status: Staff has received the staff requirements memo and the final edited version is due to SECY on October 7, 1985.

Section: 301 of NWPA: DOE Mission Plan

! Action: DOE issued the final Mission Plan on July 9,1985 and NRC has testified concerning the Mission Plan before both Houses of Congress in early September.

j Status: NRC has been requested to testify concerning the Mission Plan and

, other high-level radioactive waste topics before the Senate

] Subcommittee on Nuclear Regulation (Simpson) on October 29, 1985.

Section: 114(e) of NWPA: Project Decision Schedule Comments i

l Action: DOE had requested comments on the draft Project Decision Schedule by l September 13, 1985 (SECY-85-282).

Status: The Commission has voted to approve the comments with certain modifications. SECY expects the Commission to submit the comments to DOE soon.

Section: 114(f) of NWPA: Preliminary Determination of Site Suitability l Action: The Commission met with representatives of States and Tribes on

Friday, September 6, 1985 to receive their views on preliminary

! determination.

ENCLOSURE C OCT 41985 l

Status: The Commission requested OGC to examine whether NRC is legally required by NWPA to take any action now in response to the current DOE position on the timing of the preliminary determination. In a memo to the Commission on September 24, 0GC advised that the Commission had no need to act now, but should not remain silent on the issue.

NFS-Erwin Strike by OCAW members continues. NFS is conducting limited operations of the HEU production, scrap recovery and R&D facilities. No problems with operations have arisen to date.

Sequoyah Fuels Corporation, Gore Oklahoma On September 26, 1985, Administrative Judge John H. Frye, III issued a Memorandum and Order in the matter of Sequoyah Fuels Corporation (SFC) informal hearing on an amendment request for construction and operation of a facility to convert depleted uranium hexafluoride to tetrafluoride. The Memorandum and Order admitted as parties to the hearing the Native Americans for a Clean Environment Client Council, the Cherokee Nation, the Citizen's Action for a Safe Environment, Mr. Ed Henshaw, the Arkansas Peace Center, the Town of Gore, the Oklahoma Department of Health, and the National Water Center. The NMSS staff will not participate as a party .in the hearing. A schedule was established which provides for SFC to respond to the allegations of the petitioners no later than October 15, 1985.

Conference of Radiation Control Directors On September 22-24, 1985, a member of FCUP staff attended the meeting of the Conference of Radiation Control Directors, Radiation Measurement Committee in Tulsa, Oklahoma. The following topics were discussed: 1) Discussion of the Calibration Directory Questionnaire results; 2) Expansion of " General Criteria for the Operation of State Regional Calibration Labs" to include additional calibration procedures; 3) Review required frequencies of accreditation for calibration laboratories; 4) Discuss publication details of " Ionizing Radiation Measurement Criteria for Regulatory Purposes."

ENCLOSURE C OCT 41985 l

0FFICE OF INSPECTION AND ENFORCEMENT Items of Interest Week Ending October 4, 1985

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

a. EN 85-67, a Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $125,000 was issued September 27, 1985 to Commonwealth Edison Company (LaSalle Units 1 & 2). This action is based on three instances where Commonwealth Edison Company failed to ensure that modifications performed on safety-related systems were adequately controlled so that the operability of the systems was not jeopardized.

b. EN 85-68, a Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $50,000 was issued October 2, 1985 to Comonwealth Edison Company (Byron). This action is based on three separate events which involved the failure of management to follow radiation protection procedures, evaluate radiological conditions and to prepare adequate procedures.

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

. Week:

a. PNS-I-85-13, Boston Edison Company (Pilgrim), Discovery of Damaged Spent Fuel Handling Equipment.

b. PN0-I-85-71A, Various Region I Plants (Yankee Rowe, Vemont Yankee, Maine Yankee, Pilgrim), Update of Actions in Response to Hurricane Gloria.

c. PNO-I-85-72, Long Island Lighting Company (Shoreham), Y0H Security Guard Contract Negotiations / Potential Strike.

d. PN0-IV-85-49, Arkansas Power and Light Company (Arkansas Nuclear One Unit 2), Outage Greater Than Two Days.

e. PN0-IV-85-50, UMETCO Minerals, White Mesa Mill (Blanding, UT), Leach Tank Manhole Structural Failure,

f. PN0-V-85-64, Sacramento Municipal Utilities District (Rancho Seco),

Restart of Rancho Seco Following Extended Outage.

g. PN0-V-85-65, ADC0 Services Inc. (Tinley Park, IL), State of Washington Suspension of ADC0 Services, Inc. Permit for Radioactive Waste Burial,

h. PN0-V-85-66, Sacramento Municipal Utility District (Rancho Seco),

Loss of Main Feedwater Event at Rancho Seco.

1. PNO-V-85-67, Southern California Edison Company (San Onofre), Seismic Event. ENCLOSURE D OCT 4 1985 a

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

a. IE Information Notice 85-17, Supplement 1, Possible Sticking of ASCO Solenoid Valves was issued October 1, 1985 to all nuclear power reactor facilities holding an operating license or a construction permit.

b. IE Information Notice 85-79, Inadequate Comunications Between Maintenance, Operations and Security Personnel was issued September 30, 1985 to all nuclear power reactor facilities holding an operating license or construction permit, research and nonpower reactor facilities, and fuel fabrication and processing facilities using or processing formula quantities of special nuclear material.

4. Other Items

a. Senior Management Meeting Director, IE and the Director, Division of Emergency Preparedness and Engineering Response attended an internal NRC Directors' meeting on Comanche Peak in Region IV October 4,1985.

b. Watts Bar Inspection An inspection was conducted September 30-October 4, 1985 at the Watts Bar plant regarding the employee concerns program. The inspection team consisted of members from IE, NRR, and Regional representatives.

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

- Wyle Laboratories, Huntsville, AL - To observe a LOCA test of various cables being conducted for TVA.

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- Dresser Industries, Alexandria, LA - To ensure that valves and spare parts for valves are supplied in accordance with estab-lished procedures and applicable codes and standards as required by the Fort Calhoun outage package.

- Square D Company, Peru, IN - Operating coils of size 1 starters and contactors installed in Motor Control Centers supplied by Square D and installed at Shoreham may not be rated for 77.5 percent voltage operation. A discrepancy was discovered when Shoreham maintenance ordered 13 spare operating coils rated for 85 percent voltage operation.

! - Terry Turbine, Windsor, CT - To assist AE0D to find cause(s) of l OCT 4 1985 Terry Turbine overspeed trips. ENCLOSURE D l

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d. Quality Assurance Programs _

(1) Representatives of the Quality Assurance Branch, Division of Quality Assurance, Vendor, and Technical Training Center Pro-grams visited the Region IV office on October 1-2, 1985 to dis-cuss the Comanche Peak Quality Assurance Program.

(2) Representatives of the Quality Assurance Branch visited Sargent & Lundy offices in Chicago, Illinois this week to conduct inspections associated with the Hope Creek IDVP.

(3) Representatives of the Quality Assurance Branch visited Omaha Public Power District offices in Omaha, Nebraska this week to inspect modification packages associated with the Fort Calhoun outage,

e. Incident Response Drill A drill was conducted on October 2,1985 with the Palo Verde plant, Region V, and Headquarters. Participation at Headquarters included the Reactor Safety Team, Protective Measures Team, Administrative Support Team, Liason Teams, Status Officers, and one individual representating the Executive Team. During this drill the first assessment for 1986 was conducted by Headquarters representatives.- '

on the regional response capability.

f. Operations Center Tour of the NRC Operations Center was conducted by members of the

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Incident Response Branch, Division of Emergency Preparedness and Engineering Response on September 1, 1985 for the Region IV Regional Administrator, Robert Martin. This tour discussed the agency's incident response program.

g. Relocation Tabletop Exercise On October 1, 1985, a Relocation Tabletop Exercise working group session was held. Participants included members from the Incident Response Branch, FEMA and their contractor, EPA, and 00E.

h. Structural Welding Comittee Meeting A representative of the Engineering and Generic Comunications Branch, Division of Emergency Preparedness and Engineering Response attended the structural welding comittee meeting held in St. L_ouis on September 30-October 3, 1985. The purpose of the meeting regarded-possible revisions to AWS-D1.1 structural steel welding code. '

ENCLOSURE D OCT 4 1985

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1. Inservice Test Programs Workshops A representative of the Engineering and Generic Communications Branch participated in an EPRI sponsored workshop to review ASME Section XI Requirements and Utility Inservice Inspection and Inservice Test Programs at the EPRI-NDE Center, Charlotte, NC.

j. Civil Penalties Paid On September 26, 1985 payment in the amount of $50,000 was received from Commonwealth Edison Company (Quad Cities) for enforcement action (EA 84-123) relating to a violation involving the breakdown in the management control system prior to and during a reactor scram evolution. 1

k. Enforcement Coordinators Meeting A meeting was held September 27,,1985 with the Enforcement Coordina-tors and the IE Enforcement Staff, IE, in Bethesda, MD.

1. Maintenance and Surveillance Program Survey Representative of Operating Reactor Programs Branch, Division of Inspection Programs, participated in the Maintenance and Surveillance Program conducted this week at Rancho Seco, i

. ENCLOSURE D OCT 4 1985 33 l .

i 0FFICE OF NUCLEAR REGULATORY RESFARCH Items of Interest _

Week Ending October 4, 1985 TRAC-BD1/ MOD 1 The TRAC-BD1/ MODI code is a thermal hydraulic system transient code having capabilities for calculating large or small break LOCAs as well as various system transients in Boiling Water Reactors (BWRs). A workshop was held on September 17-20, 1985 by EG&G Idaho, Incorporated at the Idaho National Engineering Laboratory (INEL). There were a total of 22 attendees including representatives from Japan, the Federal Republic of Germany, Switzerland, and Mexico. The objectives of the workshop were: (1) to review the code theory and structure, (2) to become familiar with the main features and input of the code, and (3) to discuss code deficiencies and areas for further improvement.

Two draft documents, " Overview of TRAC-BD1/M001 Assessment Studies" and

" TRAC-BD1/M001 User's Guideline" have been completed for NRC comment. The first document summarizes the NRC TRAC-BD1/ MOD 1 assessment studies at the Idaho National Engineering Laboratory (INEL) while the second provides user guidelines. The user guidelines document will be distributed to the participants of the International Code Assessment Program (ICAP) in the forthcoming meeting on October 21, 1985.

Nuclear Plant Data Bank (NPDB) Meeting with LANL Staff The NPDB is a computer-based storage system for reactor plant geometric and operating data. The purpose of the NPDB is to generate TRAC-PF1 and RELAP5 input decks in response to user mesh cell definitions. The Los Alamos National Laboratory (LANL), the Office of Nuclear Reoulatory Research (RES), and the Office of Nuclear Reactor Regulation (NRR) staff met in Silver Spring on September 24, 1985 to discuss plans to improve the NPCB software and documentation and to drastically simplify the data requirements by defining a minimum data set.

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ENCLOSURE E OCT 4 1985 1

Semiscale A Quick-Look report for Semiscale test S-FS-6 (Report EGG-SEMI-7022) has been distributed. Test S-FS-6 simulated a 100 percent break of a- steam generator bottom main feedwater line down!,tream of the check valve. The principal purpose of the experiment is to evaluate the ability of NRC's best-estimate codes to predict primary to secondary coolant heat transfer and thereby determine the maximum primary coolant system pressure resulting fron this transient. The test was divided into three phases.

During the initial phase only automatic actions occurred followed by a phase during which operator actions were undertaken to stabilize the plant. Experiment results show thct the automatic actions mitigated the consequences of the feedwater line break and that the operator actions taken were adequate to stabilize and cool down the facility. The final test segment consisted of a controlled primary system cooldown and depressurization in which the upper head void collapse using the " fill and drain" and pump restart were both performed successfully.

1 Multiloop Intecral System Test (MIST) i The 10th Program Management Group Meeting (PMG) for the MIST program was j held on September 24-27, 1985 in Lynchburg, Virginia. The MIST facility will provide integral simulations of small-break loss-of-coolant accident 1 and other transients in a Babcock and Wilcox (B&W) plant geometry for use j in assessing code capability. The PMG reviewed and tentatively approved (subject to revisions agreed to at the meeting) the test specifications for the MIST program. The MIST program is currently on schedule, with shakedown testing starting within a few weeks and actual testing scheduled for the second half of FY 1986.

Severe Accident Risk and NUREG-1150 The risk rebaselining program for the reference plants continues approximately on schedule, although the Surry, Peach Bottom, and Sequoyah reviews have slipped 3 or 4 weeks because of: problems with integrating the source term code package; che necessity to analyze the results carefully regarding potential risk reduction measures, since the dominant risk contributors are changing somewhat compared to the original PRA; and the necessity to concep-tualize reasonable designs and procedures for the ATFS rule requirements, since these have not yet been implemented at Peach Bottom. LaSalle (a Mark II) has been added as a sixth reference plant to complete the spectrum of basic containment types, but the schedules have not been developed yet.

Considerable effort will be expended in understanding, characterizing, and displaying uncertainties in the risk estimates. IDCOR also will likely be ,

starting a substantial program in the area, and information exchange meetings will be conducted at appropriate times during the next 6 months.

ENCLOSURE E OCT 4 1985

a BNL Uncertainty Study

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A study is underway at the Brookhaven National Laboratory (BNL) to determine uncertainty in the severe accident source terms to the containment. The study will use regression analysis to elucidate the effect of varying inputs to the computer codes (STCP) that calculate source tems. The BNL study is intended to confirm the source term uncertainty being approximated at the Sandia National Laboratories for use in the risk estimates in NUREG-1150. The Peach Bottom TC sequence, the Sequoyah V-sequence and the Sequoyah S Hpg sequence will be completed in FY 86 and used in this 1150 study. Uncertainty estimates are needed for NRR to consider source terms and risk in the regulatory process.

USGS/ FEMA Workshop on Earthquake Hazards Mr. Leon Beratan, Chief of the Earth Sciences Branch, RES, has been invited to attend a USGS/ FEMA Workshop on Earthquake Hazards in the Puget Sound, Washington, area. The objectives of the workshop are to: (1) Review the current studies in the Puget Sound area, (2) Review societal and technical lessons learned from past earthquakes that are applicable to the Puget Sound area, (3) Review earthquake preparedness and planning programs in the Puget Sound area, and (4) Recommend actions for the next 5 years and beyond that are needed to reduce potential losses from earthquake hazards in the Puget Sound area. Included as a topic of the workshop will be the recent Chilean earthquake which was a major earthquake at a subduction zone type plate boundary similar to the situation between northern Oregon and Washington.

Earthquake hazard has been a significant factor for licensing of NPP's in the Northwest; e.g., Trojan and the WPPSS plants.

The workshop will be attended by 75 invited participants.

Publication of NUREG on blW Disposal in the Unsaturated Zone NUREG-1046, " Disposal of High-Level Radioactive Waste in the Unsaturated Zone:

Technical Considerations and Response to Comments" has been sent to the publishers. This document provides the technical issues considered by the NRC staff during development of amendments to 10 CFR Part 60 concerning disposal of HLW in the unsaturated zone. NUREG-1046 also addresses public coments received on both the proposed rulemaking and the draft version of the NUREG. The final amendments to Part 60 related to the unsaturated zone were promulgated on July 22, 1985.

ENCLOSURE E OCT 4 1985

Meeting with Japanese on International Piping Research Staff members from NRC-RES and the contractor Battelle-Columbus visited Japan fron September 10 to 20 to solicit Japanese participation in the International Piping Research Group (IPIRG). The meeting schedule included government, utilities, vendors and industrial groups. The approach taken was to provide detailed technical descriptions of the proposed IPIRG program and of the presently ongoing NRC research efforts in piping, and then to answer all questions about the philosophy, costs and potential membership of the IPIRG. As a result of this visit, it appears that Nuclear Power Engineering Center (NUPEC) will join IPIRG on behalf of Japanese industry and the government.

The IPIRG has been initiated by NRC in cooperation with EPRI in an effort to develop a unified analytical and experimental technology that is agreed upon on an international basis. The objective of IPIRG is to develop, improve and verify engineering methods for assessing the integrity of nuclear power plant piping containing defects, especially under severe dynamic and seismic loading. This program then, is directly responsive to research recommendations of the NRC Piping Review Committee, which call for tests of degraded and high energy piping for ductile fracture mechanics analysis validation, and for determination of a replacenent pipe rupture and pipe crack criterion, if the research show them to be required. The technology will provide more confidence in assessments of the significance of detected flaws in piping and pipe components.

I ENCLOSURE E OCT 4 1995

2 ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING OCTOBER 4, 1985 International Meetings The following international meeting notices supplement those previously i announced:

, November 11-15, 1985, Vienna, Austria - IAEA Technical Committee to Prepare a Safety Document on the Assessment of Occupational Intake of Radioactive Materials November 18-22, 1985, Vienna, Austria - IAEA Technical Committee Meeting on Procedures for Assessing the Reliability of Radionuclide Environmental Transfer Model Predictions November 25-28, 1985, Madrid, Spain - IAEA and NEA Heeting on Recent Trends in Primary Circuit Technology IAEA Vacancy Notices The following vacancy notices from the International Atomic Energy I

Agency in Vienna, Austria have been posted on NRC bulletin boards:

P-3 Supervisor, Radiometry Laboratory for Measurement of Nuclear Fuel Materials, Division of Research and Laboratories, Department of Research and Isotopes

< . P-5 Systems Analyst, INIS Section, Division of Scientific and Technical Information, Department of Nuclear Energy and Safety

P-2 Development Programmer, Computer Section, Division of Scientific and Technical Information, Department of Nuclear Energy and Safety P-3 Atomic Physicist / Development Programmer, Nuclear Data Section, Division of Research and Laboratories, Department of Research and Isotopes P-5 Quality Assurance Engineer, Reactor Engineering Section, Division of Nuclear Power, Department of Nuclear Energy and Safety 4

P-5 Section Head, Section for System Studies, Division of Development and Technical Support, Department of Safeguards P-4 Recruitment Specialist, Recruitment Unit, Staff Administration ENCLOSURE G Section, Division of Personnel, Department of Administration OCT. 4 1985

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International Visitors On Monday Mr. Masamichi Chino of the Japan Atomic Energy Research Institute, Mr. Yoshitaka Arakawa of the Ministry of International Trade and Industry, and Mr. Tetsu Imai of the Japan Electric Power Information Center toured the NRC Operations Center and met with staff of the IE Division of Energency Preparedness and Engineering Response.

On Tuesday Mr. C. d'Orval, Head of the Water Reactor Department, Mr. P. Hammer, Assistant to the Director of the Institute for Industrial Research and Development, and Mr. B. Barre, Chief of the Reactor Core Studies and Systems Branch, of the French Atomic Energy Commission (CEA), met with representatives of NRR and IP to exchange views on

improvements for future LWRs. In the course of the discussions it was stated that CEA funds and performs a broad program of LWR R&D.

Framatome and Electricite de France have access to this CEA development I

technology. N-4 is the most advanced LWR design currently under construction in France. Early feasibility studies are underway by CEA and Framatone that will eventually lead to the next generation preliminary design.

On Wednesday a twelve-member Japanese Pressurized Thermal Shock Survey Team, headed by Prof. Hiroyuki Okamura of the University of Tokyo, met RES and NRR representatives to discuss the status of Japanese and U.S.

programs in this field.

On Friday Mr. H. G. Rumpf of TUV/Bavaria, accompanied by Dr. K. Frank and Mr. J. Ruzbacki of UG U.S.A., visited NRC to discuss with members of NRR, IE and NMSS the way NRC regulates U.S. utilities. TUV/Bavaria is exploring the possibilities of providing expert nuclear advice to interested U.S. utilities or other companies.

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ENCLOSURE G 1

00T 41985 l

0FFICE OF STATE PROGRA.'iS ITEMS OF INTEREST WEEK ENDING OCTOBER 4, 1985 Dakota Low-Level Radioactive Waste Comnact -

The South Dakota Suoreme Court has upheld the constitutionality of a State law that requires voters to approve the State's entry into an Interstate compact for low-level radioactive waste. The Court added that the decision of the voters is binding on the State. A special election to consider a compact with North Dakota is scheduled for November 12, 1985.

. Review of the North Dakota Program A review of the North Dakota radiation control program will be performed October 22-25, 1985.

Training Course An Inspection Procedures Course for State regulatory personnel will be held October 21-25, 1985, in Sacramento, California.

ENCLOSURE H OCT 4 1985

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OFFICE OF RESOURCE MANAGEMENT j,

Items Of Interests

, Week Ending October 4, 1985 i

i FY 1986 Continuing Resolution i

i Based on receipt of an apportionment from OMB, allotments were issued to all

! program offices and regions for the period of the FY 1986 Continuing l

Resolution (October 1,1985-November 14,1985).

Conversion to Direct Deposit / Electronic Funds Transfer (DD/ EFT) Syster. l2r i Payroll Allotments I

The Division of Accounting and Finance completed the conversion of payroll allotments to financial organizations from the composite check method to the j DD/ EFT method. The new procedure was implemented as of Pay Period 20 affecting payroll allotment deposits on the payday of October 8,1985. This

project required coordination with the Department of Treasury and over 200 financial organizations.

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ENCLOSURE I l

j ocT 41985

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REGION III STATUS REPORT

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DAVIS-BESSE LOSS OF FEEDWATER EVENT October 4, 1985 Plant Status The plant remains in cold shutdown. The circulating water canal is drained.

Decay heat removal loop No. 1 is drained for maintenance. Emergency Diesel Generator #1 is inoperable due to an electrical control problem, troubleshooting is in progress.

ENCLOSURE L OCT 41985

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--i A. EQUIPMENT STATUS (F0LLOWS TABLE 5.1 IN NUREG 1154)

I TROUBLESHOOTING /R0OT CAUSE COMMENTS RIII ACTIONS yITEM DETERMINATION ACTIVITIES I. Main Feedwater Cause determined to be component MFPs were tested on 09/05- Region III is monitoring Turbine failure in speed control circuit. 06/85 with no problems noted. licensee evaluation of Revised report issued 08/30/85. reliability of the MFPs.

2. Closure of MSIVs** Cause determined to be that circuit More testing will be scheduled RIII monitoring licensee's was overly sensitive to momentary later. Specialist from NRR activities and observing selected activities, system perturbation. Revised will observe testing as report issued 09/07/85. Trouble- required.

shooting now in progress should not effect root cause determination.

3. Steam Safeties,** Defective electronic module in Remaining ten MSSVs have been Atmos. Vents. ICS likely cause of problem with removed and will be shipped RIII following licensee atmospheric vent valves. Revised to Wylie for full flow steam activities.

report issued 09/06/85. MSSVs testing. Vendor Programs being evaluated. Branch has been notified.

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

report issued 09/09/85. Governor from #2 AFWPT has been removed and sent to Woodward along with two spare governors for inspection and modifications.

Governor for #1 AFWPT is being replaced with a new governor.

5. AFW Containment ** Causes were incorrect torque switch Additional dp and flow testing RIII following licensee Isolation Valves bypass settings and inadequate test is being evaluated. activities.

and maintenance procedures. Revised report issued 08/29/85.

6. Steam Supply Valve ** Completed and revised report Activities completed. RII,I to observe any issued 09/09/85. Valve will be Additional testing additional testing, to AFPT No. 1 g inspected internally with a is planned in hot p borescope. standby.

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3 TROUBLESHOOTING / ROOT CAUSE RIII ACTIONS ITEM DETERMINATION ACTIVITIES COMMENTS

' g . Source Range NI** Revised report issued 09/19/85 Licensee will replace the RIII observing activities. '.

m on NI-2. NI-2 failed due to a containment cable penetration 2

defective containment penetration module for NI-2. NI-1 is module. The root cause of the being monitored and is penetration failure is not yet functioning correctly.

known. Revised report issued 09/16/85 on NI-1. Root cause was bad connection between detector and cable.

8. PORV** Completed and report sent to NRR Valve will be rebuilt (as RIII observing activities.

08/23/85. Root cause not deter- needed). Two spare PORVs have Vendor Programs Branch has mined. been rebuilt by Crosby, and been notified.

will be shipped to Marshall Steam Station in Terrell, N.C.

for testing next week.

9. S/U Feedwater Control Completed and revised report issued Work complete. None.

l Valve 08/29/85. The valve functioned correctly during the June 9 event.

10. Recovery of AFP** Completed and revised report issued Procedure has been revised and RIII to review operator Turbine 08/30/85. Training and procedural operator aids (instructions) training program to j

deficiencies identified, will be posted at the turbines, assure proper operator

1. 2 AFWPT trip throttle valve actions.

has been removed for inspection.

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11. AFP No. 1 Suction Revised report issued 09/17/85. Individual pump suction RIII observing activities.

Transfer Root cause determined to be strainers will be removed and i

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excessive pressure drop across the comon suction strainer will i comon strainer caused by be replaced with a coarser mesh transient flow variations. strainer.

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12. Turbine Turning Gear * ,

! 13. Control Room HVAC*

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! o TROUBLESHOOTING / ROOT CAUSE

OTEM DETERMINATION ACTIVITIES C0f# TENTS RIII ACTIONS  ;

Completed and revised report issued New drain header has been RIII to monitor.

• ]4. Turbine Bypass Valve 08/29/85. Valve failure caused by installed. New valve operator -

g m water hammer. has been shipped from vendor.

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

**Show change in status from previous update.

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B. REGION III STAFF ACTIONS AS ASSIGNED BY W. DIRCKS MEMO 0F AUGUST 09 1985 1

l - 1. Item: Adequacy of the licensee's management and maintenance activities ca STATUS /COPMENTS S ACTION

! a. (b) Evaluate and take action on the Region III Davis Besse study group licensee's response to findings established to review LER's, DVR's cs (Deficiency Reports) and enforcement i 2R concerning management practices

! (e.g., control of maintenance history and determine if licensee's and l programs and post-trip reviews). Region III's actions were ad'quate and appropriate. Inspections are ongoing.

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! 6. Item: Reliability of the AFW containment isolation valves and other safety-related valves 1 STATUS / COMMENTS

ACTION (a) Monitor the licensee's trouble- Region III inspection specialists from the l

shooting activities Division of Engineering and the Resident Inspectors are monitoring the licensee's troubleshooting activities. (See Table A l on Equipment Status.)

i j (e) Determine that the procedures for A Region III specialist is following the l adjustments of the AFW isolation licensee's actions and has reviewed the valves such as torque switch bypass licensee's procedures for adjustment of j torque switch bypass switches and torque switches are clear and proper, and 4

that associated training programs switches. The licensee has purchased a

! are adequate. Confirm that adjustment MOVATS machine to aid them in the setting of all limitorque operated valves.

! settings are consistent with plant I procedures.  ;

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7. Item: Adequacy of emergency notifications ACTION STATUS / COMMENTS ca C3 (a) Verify the adequacy of the licensee's Region III Emergency Preparedness has 4- procedures and training for the report- reviewed the licensee's training and

-3 ing of events to the NRC Operations procedures for reporting of events to the NRC. One violation of NRC requirements was SR found. Region III is reviewing the licensee's reporting per 10 CFR 50.72 and 10 CFR 50.73.

8. Item: Reliability of AFW pump turbines l

ACTION STATUS / COMMENTS (a) Monitor the licensee's trouble- (See Table A.)

shooting activities including possible hot plant operation to confirm failure mode.

(d) Verify that the AFW system has been NRC testing review group consisting of IE, adequately tested to confirm system NRR, and Region III members established and configuration involved with design will review AFW system testing. First team basis events. meeting scheduled for October 8,1985 in Region III.

(e) Review the implementation of the A training assessment team inspection was operator training program to assure completed on 9/26/85. Region III will prcper operator actions, such as follow the licensee corrective actions resetting of trip throttle valve. relative to team findings.  ;

9. Item: Reliability of the PORY ACTION STATUS / COMMENTS (a) Monitor the licensee's trouble- Troubleshooting complete. Two spare PORVs shooting activities have been rebuilt by Crosby and will be ni shipped to Marshall Steam Station in Terrell, Ei N.C. for testing next week.

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s Other Activities 1

l The licensee stopped work 9/25/85 on all nuclear safety related work due to l problems with control of vendor manuals. Some work resumed on 9/27/85 after

controlling procedures were modified and plant personnel were instructed on the

proper use of vendor manuals. _

The new electric motor driven startup feedwater pump (SUFP) is in place.

Installation of pipe and valves is about 75% complete. Conduit installation, ,

cable pulling and wire termination is in progress. The old SUFP has been

( electrically disconnected.

Evaluations and inspections relating to the auxiliary feedwater system

]'

restraints are continuing. Baseline inspections of the No. 2 HPI and the No. 2 LPI systems are continuing. A hanger for the No. 2 HPI system was determined to inoperable. The licensee is evaluating the effect of the inoperable hanger >

j on the operability of the HPI system. Eight additional licensee inspection ,

i teams have begun inspection of 800 pipe supports in containment.

) Nonconformance Reports (NCRs) have been written against 679 of the 716 pipe 1 supports inspected so far. Licensee's engineering department has received 630 j NCRs for evaluation. Two hundred eighty-five NCRs have been dispositioned, twenty five require rework.

, A Region III specialist discussed the status of motor-operated valve testing

! with the Davis-Besse maintenance and engineering staff. They are reporting i that approximately 70 of a total of 166 safety-related motor-operated valves j en site have been tested. A number of open items were identified with respect i to 1) closure thrust capabilities of the limitorque o .

I of findings resulting from the MOVATS TESTING, and 3)perators, design control of2)the evaluation j limitorque control switch setting (both torque and limit switches). Testing i using the MOVATS system is expected to resume as soon as copies of the newly j revised and approved test procedures are available from word processing. l t '

Corrective Action Plans j Corrective action plans to repair equipment that malfunctioned during the j event have been issued for the following equipment items. Work is in progress  ;

< on most of the action plans. Item numbers correspond to Table 5.1 in NUREG >

1154.

[

l ITEM PLAN DATE ISSUED l 4 t

1. Main Feedwater Turbine 4 08/26/85 (

1 6 09/03/85

2. Closure of MSIVs 1 09/04/85 ,

i

4. Auxiliary Feedwater Turbine 1 09/20/85(Rev.1)

! 5. AFW Containment Isolation Valves 1 09/07/85(Rev.1) '

}

6. Steam Supply Valve to AFPT No. 1 1 08/29/85 '

i ENCLOSURE L i i

l OCT 41985 8 l

s l

7. Source Range NI-1 1/2 09/26/85 (Rev. 1)

Source Range NI-2 1 09/23/85

8. FORY 1 09/09/85 (Rev. 2)

9. S/U Feedwater Control Valve 1 09/08/85 (Rev. 3)

10. Recovery of AFP Turbine 1 09/09/85

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

14. Turbine Bypass Valve 1 09/05/85 (Rev. 1) 2 08/26/85 Davis-Besse Course of Action Report submitted on 09/09/85 is under review. A separate inspection plan is being developed based on this review.

l I

ENCLOSURE L OCT 4 1985 9

o

• Planned Meetings ACRS Subcomittee Meeting on Valve Reliability - October 8,1985.

ACRS Full Comittee Meeting on Davis-Besse June 9,1985 event -

October 10, 1985.

Meeting on Control Room Design Review - October 9,1985.

AFW Hanger Evaluation Meeting at Davis-Besse - October 9, 1985.

Planned Special Inspections and Evaluations Annual INP0 Evaluation - September 30 - October 11, 1985.

IEB 80-11 and Water Seepage Inspection - RIII - October 8,1985 Miscellaneous 4

l 1

ENCLOSURE L OCT 4 1905

s l

,i i ITEMS ADDRESSED BY THE COMMISSION - WEEK ENDING OCTOBER 4, 1985 '

i A. STAFF REQUIREMENTS MEMORANDUM - AFFIRMATION / DISCUSSION AND VOTE, 3:30 P.M.,

TUESDAY, SEPTEMBER 17, 1985, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE i (OPEN TO PUBLIC ATTENDANCE) Memo SECY to W. Dircks and H. H. E. Plaine dated 9/30/85 _ ,

I. SECY-85-295 - Commission Review of ALAB-800 (Shoreham

" Vital Equipment" Decision)

The Commission, by a 5-0 vote, approved an order that announces that the Commission will defer indefinitely publication of an l

opinion explaining the Commission's June 11, 1985 decision requiring LILCO to treat part of its alternate AC system as i vital equipment.

j (Subsequently, on September 24, 1985 the Secretary signed the r order.)

II. SECY-85-178 - Final Amendments to Uranium Mill Tailings -

Rule to Implement EPA Stability and Radon Release Standards l I The Commission, by a 5-0 vote, approved final amendments to 10 CFR Part 40 that conform to and implement stability and radon l release provisions of the EPA's final standards for uranium and  !

I l thorium mill tailings as contained in SECY-85-178.

j The Federal Register Notice should be forwarded for signature and publication in the Federal Register. l (EDO) (SECY Suspense: 10/18/85) l i The Commission also requests that the staff provide it with the

} proposed rule dealing with the ground-water provisions of the ,

! UMTRCA as soon as possible. '

j (EDO)

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l ENCLOSURE O i

OCT 4 1985

L..

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i 4 l B. STAFF REQUIREMENTS - CONTINUATION OF BRIEFING ON DAVIS-BESSE, 9:30 A.M., ,

< WEDNESDAY, SEPTEMBER 18, 1985 COMMISSIONERS' CONFERENCE ROOM, D.C.,  !

0FFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to W. Dircks dated 10/1/85 1

! The Commission continued the discussion with the NRC staff of l l their response to the June 9, 1985 event which resulted in the j 4 loss of all feedwater at the Davis-Besse plant.*

I Commissioner Asselstine suggested that at the next meeting that the Commission has with NUMARC, one of the topics of discussion should be plant maintenance. He suggested that questions for

.l NUMARC consideration should includes ,

i

! 1. What is NUMARC doing in the plant maintenance area, t including NUMARC's schedule and plan of action with  !

! respect to all utilities? ,

I j 2. What priority does NUMARC give to improving the j maintenance program of the utilities? t

3. When does NUMARC expect the utilities to upgrade their [:

j maintenance programs?

)

i 4. To what extent is NUMARC obtaining the benefits of existing j

plant maintenance programs? j i

] 5. What are the indications of a good maintenance program?

i r l 6. To what extent is NUMARC obtaining the benefits of  ;

j maintenance programs in other countries such as Japan? t 7 To what extent does NUFARC make a distinction between safety related, important to safety and non-nafety related i j

components in the maintenance program, t

! Chairman Palladino noted that the Commission would expect continued close coordination between the staff and the Com- I mission on Davis-Besse and raised the issue of whether the '

Commission should be the body to approve restart. Commis-sioners are requested to advise SECY of their views no later  !

than September 30, 1985. l i

I i

• On Tuesday, September 17, 1985 the Commission met with t representatives of Toledo Edison to discuss the Davis-Besse j event. Although the staff was scheduled to follow the briefing l by Toledo Edison, in the interest of time the Commission i decided to reschedule the staff portion of the briefing for

September 18, 1985. j 4

i l

l ENCLOSURE O  !

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l MI 41985 l

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g NRR NEETING NOTICES *

! $ OCTOBER 4, 1985 DOCKET APPLICANT / ,

DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 12/9/85 50-346 P-110 Discussion of Technical aspects Toledo Edison Co A. DeAgazio 9:00 an -

Bethesda and implementation schedule

, for detailed control room design

• review at Davis-Besse 10/9/85 50-219 Rm 5215 Discuss questions on info needed GPU Nuclear Corp J. Donohew 9:30 an Air Rights III by staff to complete review of -

4550 Mont. Ave. the Oyster Creek control roca Bethesda within the Detailed Control Room Design Review NUREG-0737 Item I.D.1. ,

10/9/85 50-289 TMI-I Site To conduct a design review GPU Nuclear J.Thoma 9:00 am Harrisburg, PA of circuitry for automatic initiation of auxiliary feed-water system following com-pletion of long-term modifications 10/10/85 50-259/260/ P-422 To discuss TVA's Integrated TVA- R. Clark 9:30 am 296 Bethesda Schedule for NRC-Required (Browns Ferry 1,2,3)

Modifications ,

o 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 i

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NRR MEETING NOTICES

• DOCKET APPLICANT /

DATE/TI9E NUBSER LOCATION PURPOSE ATTENDEES , NRR CONTACT 10/16/85* 50-244 P-422 To present status report on Combustion Engrg*, M. Fairtile 9:00 am 50-305 Bethesda Upper Plenum Injection Rochester Gas & Elec.

Evaluation Model development. Wisconsin Public. Serv.

10/17/85 P-110 Discuss woth Owners. GE and BWR Owners Group F. Cherny 9:00 am Bethesda T/R Representatives GE, T/R Representatives ,

• NOTE: This meeting will be closed due to the proprietary nature of the information that will be discussed t

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l l

l 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.

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l c NHSS MEETING NOTICES S

, FOR WEEK ENDING:10/4/85

• Division of fuel Cycle and Matcrial Safaty .

n -

$ DOCKET -

ATTENDEES /

NRC CONTACT NUPBER LOCATION PURPOSE APPLICANT

"'DATE/TIPE 10/5-12/85 Vienna, IAEA Advisory Group to prepare a D. Cool (FC) Cool -

(Dates incorrectly Austria Safety Series document on "The reported last week) Application of the Principles of Rad-iation Protection to Sourcds of Potential Exposure, with Special Reference to Radioactive Waste Repositories."

~

10/9/35 70-25 Willste To discuss the new organization and Dr. M. E. Remley (RI) Ketzlach 8:30 am SNM-21 License Amendment Requirements N. Ketzlach (FC) i with Rockwell International (RI).

10/9/85 70-364 Parks Meeting to discuss remedial action M. Austin (B&W) Loysen .

(Location changed) Township, efforts on the upper slope burial site P. Loysen (FC) l PA at Babcock & Wilcox Parks Township site. J. Roth (RI) l l 10/15/85 Frankfurt, Battelle Frankfurt Fire and Explosion Dr. J. Hofmann, Ayer l FRG Modeling Status. et al. (Battelle) l J. Ayer (FC) 10/17-18/85 Karlsruhe, Radioactive Contamination Behavior Dr. H. Schmidt, Ayer l ~

FRG in Fires --E.K. Experimental Results. et al. (Euratom)

J. Ayer l 10/18/85 Karlsruhe, Reactor Containment Aerosol Experiments Dr. W. Schock Ayer l FRG in West Germany. (Kernforschungszentrum) l J. Ayer (FC) -

! 10/18/85 Bethesda, Present talk on "NRC Licensing" at the P. Vacca (FC) Vacca i 9:00-11:00 am MD Naval Hospital. (Medical Officers

, Course in Nuclear Medicine and Radio- '

l m isotope Techniques) 5 5

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E NMSS MEETING NOTICES I[

FOR WEEK ENDING: 10/4/85 .

• Division cf fuel Cycla cnd Materini Safcty . (page 2) .

DOCKET ATTENDEES /

PURPOSE APPLICANT NRC CONTACT DATE/ TIE NUtBER LOCATION 10/19-11/1/85 Vienna, Serves as U.S. expert or observer on J. Cook (FC) Cook Austria a Technical Comittee on the Assessment of the Radiological Impact from the Transport of Radioactive Materials (I AEA).

10/21/85 Bologna, LA Experiments with Radioactive Dr. V. Prodi Ayer Italy Contamination in Fires. (University of (U. of Bologna) .

Bologna and Lavora Ambiente) J. Ayer (FC) 10/24/85 Aberdeen Present talk on "NRC Licensing Update." P. Vacca (FC) Vacca 9:00-9:50 am Proving (U.S. Army Environmental Hygiene Agency, Ground, Nuclear Medicine Science Officer .

MD Conference)

Division of Waste Manacement 10/15/85 W111ste Building To meet with Texas LLW WMLU staf f DMartin Radioactive Waste Disposal Authority 10/16-18/85 Albuquerque, NM. Society of Mining Engineers P9tataraja MNataraja Meeting - and present speech NTanious

" Rock Mass Characterization for Geologic Repositories" DIVISION OF SAFEGUARDS None i P

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, IE MEETIriG fiOTICES l $

l DOCKET ATTEriDEES/

! DATE/ TIME fiUMBER LOCATI0ft PURPOSE APPLICAfiT fiRC C0flTACT 1

10/8/85 FEMA Retion III offices Emergency preparedness Div'sion of Emergency E. L. Jordan (Philadelphia,PA) issues in Pennsylvania Preparedness and i Engineering Response, IE 4

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f h RES MEETING NOTICES October 4,1935 i DOCKET ATTENDEES /

l DATE/ TIE NLH3ER LOCATION PURPOSE APPLICANT NRC CONTACT L

10/13-11/85 130-SS Integral Facility Scaling Review 11tg RES staff Solberg i ,

10/11/85 Willste Review progress and direction of grant Scott Scott Bldg. program being conducted at Texas A&M

regarding high burnup fuel perfonnance.

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October 4, 1985 8

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n cs RII MEETING NOTICE SI DOCKET ATTENDEES /

LOCATION PURPOSE APPLICANT NRC CONTACT DATE/ TIME NUMBER RII Office Enforcement Conference Licensee, Regional Walker 10/8/85 10:00 am South Carolina Electric Administrator and and Gas Company - Summer Selected RII Staff facility Members RII Office Enforcement Conference Same as above Walker 10/9/85 2:00 pm' Florida Power & Light Co. -

Turkey Point facility Russell Bldg. Operator Licensing Meeting RII Reactor Licensees, Wilson 10/10-11/85 Atlanta, GA Applicants for Operator Licenses, NSSS Vendors, Reactor Vendors & Architect Engineers I

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