ML20151H658

Weekly Info Rept for Wk Ending 830422

ML20151H658
Person / Time
Issue date:	04/29/1983
From:	Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To:
References
WIR-830422, NUDOCS 8305040777
Download: ML20151H658 (42)

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April 29, 1983 For: The Coanissioners From: T. A. Rehm, Assistant for Operations, Office of the EDO

Subject:

WEEKLY INFORMATION REPORT - WEEK ENDING APRIL 22, 1983 A summary of key events is included as a convenience to those Connissioners who may prefer a condensed version of this report.

Contents Enclosure A

Administration Nuclear Reactor Regulation B Nuclear Materia'l Safety and Safeguards C D

Inspection and Enforcement E

Nuclear Regulatory Research F

Executive Leg?1 Director Inte national Programs G H

State Programs I*

Resource Management Analysis and Evaluation of Operational Data J ,

Small & Disadvantaged Business Utilization & Civil Rights K*

Regional Offices L*

M*

CRGR Monthly Pepcrt Executive Director for Operations N*

Items Addressed by the Commission 0 P

Meeting Motices

• Uo input this week. ~__q ,/

/,k1WE(4 T. A. Rehm, Assistant for Operations Office of the Executive Director for Operations 8305040777 830429 PDR COMMS NRCC WEEKLYINFDREPT PDR FOR SUBSCRIBERS

Contact:

ONLY T. A. Rehm, ED0 492-7781

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HIGHLIGHTS OF WEEKLY INFORMATION REPORT I

Week Ending April 22, 1983 NRC Employee Rebadging-Based on SECY-82-330, the Commission approved modifications to the NRC Personnel Security Program. Such modifications will result in significant cost savings without adversely affecting the NRC security program. Approximately 500 out of 800 enployees have been rebadged to reflect their current clearance level, f!RR At 2:50 p.m. on April 12, 1983 with the R. E. Ginna reactor in the cold shutdown mode, the RHR cooling to the reactor cooling system was interrupted for 12 minutes. During the 12 minutes that the pumps were inoperable, the RCS tem-perature increased 15 F. Region I wes notified by telephone within an hour of the event.

Millstone Nuclear Power Station, Units 1 and 2 Millstone Station was granted a one-time schedular exemption from the require-ment for an Annual Emergency Preparedness Exercise. The test has been rescheduled to October 1983.

Sioni,ficant Enforcenent Action A f!ctice of Violation and Proposed Imposition of Civil Penalty in the amount of

$500 was issued /pril 21, 1983 to John R. Sinkey, M.D. (EN 83-24), Toledo, Ohio.

Quality Assurance

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Second querterly report on the inplementation of QA initiatives and the Ford Amendment (covering the period January 1 - Ilarch 31,1983) was forwarded to EDO 4/18/83.

RES FLECHT SEASET The FLECHT SEASET Program Management Group (PiiG) authorized Westinghouse to tear down the 163 Blocked Bundle Facility because no additional testing is conten-plated for this facilty.

International Visitors 4

On Thursday and Friday f tr. Guenter Langer of the Battelle Research Laboratory in Frankfurt, Gernany toured SNL cnd discussed hydrogen control research.

APR 2 21983

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OFFICE OF ADMINISTRATION Week Ending April 22, 1983 ADMINISTRATION OF THE FREEDOM 0F INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Received 258 14 Granted 167 1 Denied 39 7 Pending 52 6 ACTIONS THIS WEEK Received Lyle D. Graber, Requests four listed letters regarding the Saxton Test NUS Corporation Reactor (Docket 50-146) to be placed in the POR.

(83-188)

Leah P. Tremper, Requests a copy of all approved staffing plans for FY 83 NTEU Steward and FY 84 for the Office of Administration.

(83-189)

John Scudder Requests lists of Plant Managers, Training Managers, (83-190) Radiation Control Officers and individuals holding reactor operator licenses that are either. active or expired.

Max 0. Truitt, Jr., Requests, on behalf of International Business Machines Jane Tucker Dana Corporation, four categories of documents regarding .

Wilmer, Cutler, Book Mart International, Inc. and Daniel L. Hall.

& Pickering (83-191)

Diane Curran, Requests all dc;uments regarding the design, composition, Harmon & Weiss and performance of the Westinghouse Model F steam (83-192) generators.

Harvey S. Sands, Requests a copy of Request for Proposal No. RS-NMS-82-027, Ebasco Services " Licensing Technical Assistance".

Incorporated (83-193)

Paul Thurmond, Requests a copy of the technical proposal awarded for NUS Corporation Contract No. NRC-03-83-107.

(83-194)

CONTACT: J. M. Felton 492-7211 -

ENCLOSURE A APR 2 21983

.. . 2 Received, Cont'd Mary M. Johnston, Requests eight categories of documents regarding the Citizens for ~ Fermi Nuclear Power Plant, Unit 2.

Employment & Energy (83-195)

Jim Pedro, Requests a copy of Safety Reactor Operating Experience

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NUS Corporation Report 73-8 dated August 1973.

(83-196)

Granted Charles Barnes In response to a request for three listed documents (83-126) regarding the University of Kansas Research Reactor, made available the requested records.

David R. Hodas, In response to a request for information regarding the Potter and investigation of allegations made by Lawrence Berstler, Carmine, P.A. made available one document.

(83-140)

Steven Aftergood, In response to a request for a copy of the study and Comittee to recomendations paper by the Commission's Office of Bridge the Gap Policy Evaluation regarding the replacement of (83-142) Highly Enriched Uranium with Low Enriched Uranium in research reactors, made available a copy of the memorandum.

M. Chain Robbins, In response to a request for a copy of the license granted

' Republic Steel to Swank-Metacon, made available a copy of the requested Corporation license.

(83-172)

Lloyd J. Ginerette In response to a request for a breakdown of professional (83-174) employees within the NRC by offices, race and sex, made available the requested information.

A. Kranish, In response to a request for a copy of the Engineering Trends Publishing Evaluation Report -- 1125/1131 and the review of Inc. recommendations by the Office of Analysis and (83-179) Evaluation of Operational Data staff, and documents relating to Ray Miller, Inc., made available a copy of the engineering evaluation report. Informed the requester the documents regarding Ray Miller, Inc. are already available at the PDR.

Mary Ann Brolin, In response to a request for a list of 1982 and 1983 KLM Engineering publicly available SECY papers, made available a (83-182) copy of the requested lists.

APR 2 21983 ENCLOSURE A

Granted, Cont'd John C. Houston, In response to a request for all grant applications, The Fairness Comittee awards, contracts and cooperative agreements to the Against Tax Funded League of Cities and Conference of Mayors over the -

-Politics last ten years, informed the requester that the NRC's (83-184) Division of Contracts has no documents ~ subject to this request.

Lyle D. Graber, Informed the requester that the four requested letters NUS Corporation regarding the Saxton Test Reactor are already (83-188) located in the PDR.

Denied None l

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ENCLOSURE A EPR 2 21933 l

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. WEEKLY INFORMATION REPORT DIVISION OF CONTRACTS WEEK ENDING APRIL 22, 1983 RFP ISSUED RFP No . : RS-SECY-83-400 Titl e: " Sound Reinforcement System"

Description:

To furnish and install a permanent mounted fourteen microphone sound system used to amplify and record conference room proceedings.

Period of Performance: Forty-five days for delivery and installation -

Sponsor: SECY Status: RFP issued on April 22, 1983. Proposals due May 26, 1983 PROPOSALS UNDER EVALUATION RFP No.: RS-0RM-83-500

. Title : " Cost Analysis of Proposed Changes in NRC Requirements"

Description:

Identify and estimate the costs in monetary terms of proposed changes in NRC regulatory requirements.

Period of Performance: One year Sponsor: Of fice of Resource Management Status: RFP closed on April 15, 1983. Proposals forwarded to Source Evaluators for review on April 15, 1983. Competitive range to be established on May 26,1983.

RFP No. : ED0 83-426

Title:

" Developing a Decision making Rationale for Establishing New Regulatory Requirements"

Description:

Develop decision making process incorporating a quantitative cost / benefit model for assigning priority scores to proposed new or modified regulatory requirements. The quantitative model would use attributes which are the expected values of benefits and costs or proposed regulatory values.

Period of Performance: One year Sponsor: Office of the Executive Director for Operations Status: The competitive range has been established and negotiations are scheduled for the week of May 1,1983.

CONTRACTS CLOSED-0VT NRC-10-77-108 Centennial Systems, Inc. 4/13/83 NRC-05-82-243 Boeing Computer Services, Inc. 4/20/83 ArR 2 21983 ENCLOSURE A

P DIVISION OF SECURITY ITEMS OF INTEREST Week Ending April 22, 1983 NRC Employee Rebadging Based on SECY-82-330, the Commission approved modifications to the NRC Personnel Security Program, which modified the NRC's current criteria for determining posi-tion sensitivity, the corresponding type of background investigation, and the level of clearance of NRC personnel. Such modifications will result in signi-ficant cost savings without adversely affecting the NRC security program. Appro-ximately 500 out of 800 employees have been rebadged to reflect their current clearance level.

Security Support for Hearings SEC coordinated security arrangements for ASLBP hearings in Midland, MI (Midland);

White Plains,NY (Indian Point); and Rockford, IL (Byron).

Secure Communications Facilities SEC is working with NMSS, 01E, ORM and DIP on the security aspects of their respective facilities, which will allow the trar.smission of classified information.

ENCLOSURE A A?R 2 21933 L

%Q e OFFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending April 22, 1983 R. E. Ginna At 2:50 p.m. on April 12, 1983 with the reactor in the cold shutdown mode, the RHR cooling to the reactor cooling system was interrupted for 12 minutes.

The operators were attempting to seat plugs into the hot and cold legs of the A-steam generator in preparation for limited chemical decontamination of the steam generator channel heads. The water in the steam generator was at 35 psig (air overpressure) with some leakage past the hot leg seal. The water level dropped below the hot leg and air entered the RHR suction line. The RHR pumps were manually tripped. The operators then connected the refueling water storage tank to the RHR system, vented air from the line and restarted the RHR to restore cooling. During the 12 minutes that the pumps were inoperable, the RCS temperature increased 15 F. Region I was notified by telephone within an hour of the event.

Joseph M. Farley Unit 1 - Replacement of DS-416 Type Reactor Trip UV Device During the evening of April 12, 1983, Farley Unit I was shutdown for scheduled overspeed testing and inspection of the main turbine generator.

During the outage, Alabama Pcwer Company (APCo) and Westinghouse Electric Corporation planned to replace all undervoltage (UV) devices installed in the reactor trip breakers. These UV devices (DS-416 type) were the subject of a March 31, 1983 Westinghouse advisory letter to NRC and to all licensees having the D5-416 breakers. Westinghouse had advised that certain dimensional checks were needed to detennine if UV device replacement was required. The reason stated is that a potential exists for intermittent malfunction of reactor trip switchgear with the DS-416 UV device.

NRC was given the following status of the evaluation:

1. The four breakers obtained from Vogtle site had marginal dimensions and were not considered satisfactory for use.

2. Three of four UV devices on Unit 1 failed dimensional checks. All four UV de/ ices were replaced with a new, modified UV device (Part No.

02YN193) with correct dimensional tolerances. The modification made was to enlarge grooves for the C-clip retainers as described in Westinghouse (J. Miller) letter to APCo (0. Kingsley) dated April 13, 1983.

Prestartup testing using additional test techniques per Westinghouse Technical Bulletin was performed satisfactorily.

3. Unit 2 work is scheduled to start while the unit remains at power. Due to the significance of this operation while at power, APCo has performed dry-runs of the methodology on Unit I while shut down. These dry-runs should lend added assurance that the job can be done within existing Technical Specification time constraints in a safe, controlled manner.

AFft 2 21983 ENCLOSURE B

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Joseph M. Farley Unit 2 - Replacement and Tests of Modified DS-416 Type Reactor Trip Device The Unit 2 UV replacement program has been suspended due to unforeseen problems. The first bypass breaker was removed to the test facility, a new, modified UV device installed and the 25-cycle test of the breaker was started. After nine successful trips, the breaker failed to trip on cycle number 10. Investigation is underway by Westinghouse and APCo since the three critical dimensional measurements were within allowable tolerances.

At this time, APCo considers that measurement at position 3 between the UV trip lever and the breaker trip bar specified as 0.30" minimum should also have a maximum dimension. In the interim, APCo has briefed the operating crews for Units 1 and 2 of the anomaly found during the tests of the byp&ss reactor trip breaker. New information will be forwarded to IE Region 2 which maintains the lead responsibility for IE Bulletin 83-04 resolution.

R. E. Ginna Nuclear Power Plant As a result of performing UT examination of the J tubes on the A steam gene ator feedwater ring, the licensee has found significant metal loss from the J tube walls. Ali 38 J tubes in the A steam generator have been examined with a nominal wall loss of up to 50 percent. A hole was found in one J tube approximately an inch above the weld. The licensee is preparing to examine the J tubes in the B steam generator and is evaluating various repair options.

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Kewaunee Nuclear Power Plant - Steam Generator Inspection - Small Bolt Found

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The Kewaunee Nuclear Power Plant has been shut down since March 19, 1983 for reload. Among other activities, the steam generators were inspected. In addition to finding the first tubes that needed plugging (about 10 to 12 in each generator), a small bolt was found in the secondary side of one steam generator. The bolt is about 1" to 1 1/2" long and abcut 1/4" to 5/16" in diameter. The bolt is held firmly in place by corrosion and/or the adjacent tubes. Efforts to remove the bolt were unsuccessful and, based on a safety analysis, the decision was made by Wisconsin Public Service Corporation to leave it in place. Three adjacent tubes were preventively plugged. Another similar object exists in the vicinity.

A 100 percent inspection of the tubes was performed although only 6 percent were required to be inspected by the Technical Specifications. The last inspection was in 1980.

Appendix J Exemption for Browns Ferry, Unit 1 On April 8, 1983, we granted an exemption to the two-year test interval requirements of Appendix J for Browns Ferry Unit 1 for 11 isolation valves

'for which the two-year time period would have expired on April 12, 1983. The exemption extends the time until May 6, 1983 for testing the 11 valves, although the actual extension is only expected to be three or four days.

APR k. d~V ENCLOSURE B

Exemption to Requirements of Appendix J of 10 CFR 50 for Susouehanna Steam Electric Station, Unit 1 On April 14, 1983, Amendment No. 13 to Facility Operating Licensing No.

NPF-14, Susquehanna Steam Electric Station, Unit I was issued. The amendment provides an exemption from the requirements of Appendix J of 10 CFR 50 for the first fuel cycle when perfoming local leak rate testing of Residual Heat Removal (RHR) relief valves in accordance with Technical Specification 4.6.1.2 of the Susquehanna license.

Hatch Unit 2 Duri,sg ultrasonic inspection of Hatch Unit 2 recirculation system piping welds, linear indications have been identified on one end cap of the 22-inch diameter recirculation jet pump riser header on the "B" loop. The indications are oriented circumferentially and occur intermittently for 360 degrees in the heat affected zone, primarily on the cap side of the weld.

The licensee has nct completed the evaluation of UT data for the other thru end cap welds. Similar linear indications were found in the Unit I recirculation feeder to end cap welds last year. However, the orientation of those indications was radial ratber than circumferential. The licensee is evaluating the data to determine appropriate corrective action.

The inspection is being performed by the licensee in accordance with IE Bulletin 83-02, NUREG-0313, Revision 1, and the licensee's augmented inservice inspection (ISI) program.

St. Lucie Plang Unit No. 1 Two meetings will be held with Florida Power and Light Company (FP&L) on Monday, April 25, 1983. The first meeting will be held at 11:00 a.m. with FP&L and its contractor, Combustion Engineering, in the Phillips Building, Room 428. The purpose of this meeting is to discuss the planned recovery schedule that has been developed to resolve the thermal shield problem uncovered during the current outage.

The second meeting will be held at 1:00 p.m., also in the Phillips Building, Room 428. The purpose of this meeting is to discuss FP&L plans to perform analyses leading to the elimination of the thermal shield at St. Lucie 1.

NRC representatives at the meeting will be R. A. Clark and D. Sells in the morning, joined by R. Woods and B. D. Liaw in the afternoon.

Big Rock Point Plant By letter dated April 21, 1983, Big Rock Point was granted an exemption to the schedular requirement of 10 CFR Part 50.49(g). 10 CFR Part 50.49(g) requires a submittal by May 20, 1983 listing the electrical equipment important to safety and providing a schedule for environmental qualification of that equipment. In granting a delay in the schedule until June 1, 1983, we concluded that the delay is consistent with the integrated assessment for Big Rock Point and will not delay the actual implementation of the rule.

APR 2 21983 ENCLOSURE B

Calvert Cliffs - Fire Protection Exemption - Fixed Fire Suppression (Appendix ~

R, III.G.2 and III.G.3)

An exemption from the requirement to provide a fixed fire suppression capability (Appendix R, III.G.2 and III.G.3), in the control room and the intake structures, was granted on April 20, 1983.

Millstone Nuclear Power Station, Units 1 and 2 Millstone Station was granted a one time schedular exemption from the requirement for an Annual Emergency Preparedness Exercise. The test has been rescheduled to October 1983.

ENCLOSURE B APR 2 21933

NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT April 17, 1983 - April 23, 1983 Plant Status Core Cooling Mode: Heat transfer from the reactor coolant system (RCS) to reactor building ambient.

Available Core Cooling Mode: Mini Decay Heat Removal (MDHR) system.

Standby Pressure Control System.

RCS Pressure Control Mode: _

Major Parameters (as of 6:15 AM, April 22, 1983) (approximate values)

Average Incore Thermocouples*: 91*F Maximum Incore Thermocouple *: 134*F RCS Loop Temperatures: B A

Hot Leg 88*F 86*F C'old Leg (1) 75*F 77*F 75*F 76*F (2)

RCS Pressure: 66 psig Reactor Building: Temperature: 70 F Pressure: -0.1 psig Airborne Radionuclide Concentrations:

3.0 E-7 uti/cc H (sample taken 4/21/83) 2.3 E-9 uCi/cc particulates (sample taken 4/21/83) .

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1. Effluent and Environmental (Radiological) Information Liquid effluents from the TMI site released to the Susquehanna River, after. sampling and monitoring, were within the regulatory limits and in accordance with NRC requirements and City of Lancaster Agreement.

During the period April 15, 1983, through April 21, 1983, the effluents contained no detectable radioactivity at the discharge point and individual effluent sources, which originated within Unit 2, contained minute amounts of radioactivity. Calculations indicate that less than one ten-millionth (0.0000001) of a curie of cesium was discharged.

• Uncertainties exist as to the exact location and accuracy of these readings.

l ENCLOSURE B APR 2,21983 .

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2. Environmental Protection Agency (' EPA) Environmental Data The EPA measures Kr-85 concentration at several environmental monitoring stations and reported the following results:

March 18, 1983 - March 31, 1983' Location 3 (pCi/m)

Insufficient for Analysis Goldsbo'ro ~

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Middletown 25 Yorkhaven 31 TMI Observation Center

-- The EPA Middletown Office has not received the environmental Kr-85 analytical results for the samples which were taken subsequent to March 31, 1983, from the EPA's Counting Laboratory at Las Vegas, Nevada. These results will be included in a subsequent report.

-- No radiation above normally occurring background levels.was detected in any of the samples collected from the EPA's air and gamma rate networks during the period from April 13, 1983, through April 21, 1983.

3. NRC Environmental Data Tne following are the NRC air. sample analytical results for the onsite continuous air sampler:

- I-131 Cs-137 (uCi/cc) (uCi/cc)

Samole Period

<8.5 E-14 <8.5 E-14 HP-366 April 14 - 20, 1983

4. Licensee Radioactive Material and Radwaste Shipments

-- On April 18, 1983, 75 drums,of Unit 1 and Unit 2 contaminated laundry were shipped to Interstate Uniform Service, New Kensington, Pennsylvania.

-- On April 19, 1983, four containers of equipment used during the Unit 1 Once Through Steam Generator (OTSG) repairs were returned to Westinghouse Electric Corporation (Waltz Mill Site), Madison, Pennsylvania.

-- On April 22, 1983, 109 drums containing contaminated clothing from Unit 1 and Unit 2 were shipped to Interstate Uniform Service, New Kensington, Pennsylvania.

On April 22; 1983, one drum containing Unit 1 OTSG samples (four

' wool plugs) was shipped to Battelle Memorial Institute, Columbus, Ohio.

APR 2 21983 . - ENCLOSURE B

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5. THI Occupational Exposure During the period February 1 - February 28, 1983, licensee TLD (Thermoluminescent Dosimeter) records indicated the following personnel occupational radiation exposure ranges:

Station Exposure Range Category in Rem Number of Station Personnel No Measurable Exposure 1,178 Exposure Less Than 0.1 312 113 0.1 to 0.25 67 0.25 to 0.5 - 30 0.5 to 0.75 18 0.75 to 1 46 1 to 2 18 2 to 3 Total Plant Exposure (February 1983) - 199.648 Man-Rem

• Total Unit 2 Exposure (February 1983) - 40 Man-Rem

• Unit 2 Reactor Building Entries (TLD Data) During February 1983 Number of Personnel: 239 Highest Whole Body TLD Reading (Rem): 0.364 Total Man-Rea 36.102

• Man-rem is an expression for the summation of whole body doses to individuals in a group. Thus, if each member of a population group of 1,000 people were to receive a dose of 0.001 rem (1 millirem), or if two people were to receive a dose of 0.5 rem (500 millirem) each, the total man-rem dose in each case would be one man-rem.

Major Activities

1. Submerged Demineralizer System (SDS). Testing of an SDS tank farm bypass flow path was satisfactorily completed on April 18, 1983. This test involved the routing of approximately 30,400 gallons of reactor building sump water directly from the sump through the SDS process filters without passing through, or staging to, the tank farm.

2. EPICOR II. EPICOR II processed approximately 29,200 gallons of SDS effluent, and approximately 1,500 gallons of water from the "A" contaminated drain tank during the past week.

APR 2 21983 ENCLOSURE B

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3. Reactor _ Building Entries / Polar Crane. Only one reactor building entry was completed during the week of April 17, 1983. The licensee has del'ayed many of the recovery activities in the reactor building, -

employing his engineering manpower to reevaluate the work procedures for The NRC TMI Program Office is contintiin'g to potential safety hazards.

review safety-significant work procedures, including all crane-related -

operations. A new date for the polar crane load test has not been selected. The delay in the recovery operations in the reactor building has impacted en the start of the next phase of reactor vessel data .

acquisitions; it is now not expected to start before July 1983. .

Two new evaluations for limited use of the polar crane have Theybeen involve the completed and approved by the NRC TMI Program Office.

installation of radiation shields around the reactor vessel head structures. The installation has been scheduled for next week. These tasks involve the use of the polar crane as a lifting platform to transfer material from the 305 ft. elevation to the refueling pool. A portable 5-ton hoist, attached to the main book of the polar crane, will be used to make the actual vertical lifts, while the polar crane bridge-and trolley will be used for lateral movements of the load.

Four reactor building entries have been scheduled for the week of April 24, 1983.

4 ALARA Meetina Sumary. A meeting was held on April 18, 1983, between The the NRC staff, Office of Nuclear Reactor Regulation, and G?U Nuclear.

purpose of the meeting was to allow the management of GPUN to present their program to maintain TMI-2 cleanup occupatior.a1 radiation exposures as low as reasonably achievable (ALARA). .

GPUN provided a description of their management structure and their radiological control organization, which is independent from operations organizations. They also discussed their radiation protection plan and rsey elements of the ALARA their program to maintain exposures ALARA.

program were discussed, including ALARA work and design reviews by the radiation protection organization, exposure management programs, and a dose reduction program.

The collective occupational exposures to result from the TMI-2 Thecleanup licensce's operations will be influenced by major pre; ram decisions.

programmatic decision-making process and ALARA considerations ir, that process were discussed. Examples of these decisiens were presented, e.g., wet vs. dry head lift, early vs. late head lift, decontamination vs, other dose reduction methods, and source removal vs. shielding.

Results of the ongoing three-phase reactor building dose rate reduction Phase I objectives of this program have been program met. were discussed.A data management and analysis organization has bee collect, reduce and analyze radiological data andPeriodically, recommend resolutions the licensee for' management decisions to keep doses ALARA.

is to report to the NRC the progress and planned actions on dose reduction and ALARA program issues.

ENCLOSURE B.

APR 2 21933 l l

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SDS Liner Shipments. The licensee is making preparations for shipment of.

5. This zeolite waste liner, which contains the eighth SDS liner (D20027).

'appecximately excess water.

30,000 curies, is currently being vacuum dried to r a catalytic recombiner and monitored to demonstrate non-combustible gas conditions. Shipment is t.entatively scheduled for April 28, 1983.

. 6. EPICOR II Prefilter (PF) Shipment. The scheduled shipment of EPICOR II prefilter PF-34, on April 22, 1983, was stopped On by the NRC staff a follow-up because inspection.

of concerns with the trailer's brake system.

' by a Pennsylvania certified mechanic, the six brake linings, four roller pins, and one wheel bearing were replaced before the trailer rig was established road-worthy. Notification of this problem was made with the licensee, the designated shipper (DOE), the contracted hauler, the Department of Transportation, and the Commonwealth of Pennsylvania.

The resin sampling of the

7. Purification Demineralizer Disposal Status.

"A" and "B" purification with the demineralizer vessels was completed on April 22 use of a new guide sleeve and mechanical sampling and 23, 1983,

> device. Approximately 10 grams of dry resin were collected from the "A" vessel, and approximately 100 cubic centimeters of resin and liquid were No liquid was apparent in the "A" vessel, collected from the "B" vessel.

while approximately one foot of liquid was measured above the "B" vessel's resin bed. (Both vessels contain approximately 30 cubic feet cf resin material.) The licensee is making preparation for shipment of these samples to Oak Ridge National Lab ratory r. ext week.

Future Meeting On May 2,1983, Lake H. Barrett will' meet with the Concerned Mothers of .

Middletown to discuss TM1 related issues.

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APR 2 21983 ENCLOSURE B

OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Itenis of Interest _

Week Ending April 22, 1983 Part 61 Technical Positions Approved On April 20, 1983, the Coneittee for the Review of Generic Requirements (CRGR) was briefed on the Technical Positions (TP's) on War,te Classification and Waste Form. These TP's were prepar'ad to provide guidance to waste generators for demonstrating compliancre with the low-level waste regulation, 10 CFR Part 61. CRGR gave WM the authority to distribute the TP's to all NRC licensees and to the Agreement States.

Implementation of Reporting Export / Import Data to the IAEA Under INFCIRC 207 On April 19, 1983, OMB granted approval of revision to licensee reporting instructions for export / import reporting to the IAEA. On the same day, revised instructions to all licensees were submitted to the Office of Administration for publication and subsequent distribution. The revised reporting instructions will be effective June 1,1983.

Acceptance Criteria for the Low Enriched Uranium (LEU) Reform Amendments A draft report has been received from Battelle Pacific Northwest Laboratories which contains part of the acceptance criteria for the LEU Material Control and Accounting (MC&A) Refonn Amendments. These criteria will be used by the licensing reviewer to determine if a licensee's plan is acceptable. These criteria also will be made available to the public so that a licensee will -

know the basis upon which his plan will be judged.

PP&L - Susquehanna Stream Electric Station (SSES), Low-Level Radioactive Waste (LLRW) Storage A Materials License was issued pursuant to 10 CFR Part 30 to Pennsylvania Power and Light Co. (PP&L) authorizing use of the Low-Level Radioactive Waste Holding Facility at its Susquehanna Stream Electric Station. The ccncrete storage vaults will be used for contingency storage of LLRW '

generated at the Plant. The term of the license is five years. Issuance of the license, Safety Evaluation Report, Environmental Impact Appraisal and Negative Declaration are being noticed in the Federal Register.

Meeting with Gulf Nuclear / Automation Industries On April 13, 1983, the staff met with representatives of Gulf Nuclear and Automation Industries to discuss Gulf Nuclear's request to acquire the Automation Industries facility in Phoenixville, Pennsylvania (Docket No. 03-005998, License No. 37-00611-09). Gulf Nuclear explained that there

! are currently enforcement actions pending against them in Texas, including l a proposal by the State of Texas to suspend their licenses. They pointed ENCLOSURE C

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7 out that a temporary court injunction has been issued preventing immediate suspension of their licenses, but that Texas may continue to pursue suspension. *

. Gulf Nuclear explained that they did not consider the Texas enforcement actions to involve alleged violations significant enough to cause delay or an favorable decision by the NRC staff. Gulf Nuclear urged the staff to approve their acquisition of the Automation Industries facility as. expeditiously as

' possible.

Members of the staff explained that the Texas ~ enforcement actions raised the possibility that Gulf Nuclear does not have management control sufficient to assure adequate protection of the public health and safety, and that, therefore, the NRC staff has good reason to delay action on 7 the Gulf Nuclear request until more information is obtained. Furthermore, they explained that since certain relevant information may not be currently available and will only become available as the enforcement actions proceed, no prediction can be made as to how long it will take the NRC staff to render a decision. ,

Gulf Nuclear agreed to provide the staff with all available information

. relevant to the case. The State of Texas has also agreed to provide NRC with relevant information. In the meantime, Gulf Nuclear has been informed in writing that they are not authorized to assume control of the Automation Industries facility until the NRC staff has completed its review and rendered a decision.

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i ENCLOSURE C gg 2 21983

OFFICE OF INSPECTION AND ENFORCEMENT Items of Interest Week Ending April 22, 1983

1. The following Significant Enforcement Action was taken during the past week:

EN 83-24, John R. Sinkey, M.D., Toledo, Ohio - A Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $500 was issued April 21, 1983. This action is based on a violation relating to the mailing of iodine-131 diagnostic capsules to patients in violation of NRC and U. S. Postal Service regulations.

2. The following Preliminary Notifications were issued during the past week:

a. PNO-I-83-32, Public Service Electric & Gas Company (Salem - Unit 2) -

Airborne Radioactivity in Primary Containment.

b. PNO-I-83-33, Public Service Electric and Gas Company (Salem Units 1 & 2) -

Inadvertent On-Site Release of Radioactive Liquid.

c. PNO-I-83-34, Public Service Electric and Gas Ccmpany (Salem Units 1 & 2) -

Westinghouse DB-50 Circuit Breaker - Broken Undervoltage (UV) Attachment Trip Lever.

d. PNS-I-83-06, Baltimore Gas and Electric Company (Calvert Cliffs - Units 1

& 2) - Bomb Threat.

e. PN0-II-83-24, Alabama Power Company (Farley - Unit 2) - Reactor Trip Breaker Test Failure.

f. PNO-II-83-25, Florida Power & Light Cenpany (Turkey Point - Unit 4) -

- Media Interest in Fuel Loading Problem. - -

g. PNO-II-83-26, Georgia Power Company (Hatch Unit 2) - Linear Indications in Recirculation Piping.

h. PNO-II-83-27, Duke Power Company (Catawba Units 1 & 2) - Media Interest in N Ns Conference.

i. PNO-II-83-28, Virginia Electric & Power Ccmpany (North Anna Unit 2) -

Death of Employee (Non-Radiological).

j. PN0-III-83-29, Commonwe:ilth Edison Corpany (LaSalle - Unit 1) - LaSalle County Station Shutdown.

k. PN0-III-83-30, Henry Ford Hospital (Detroit, MI) - Reported Possible Overexposure.

1. PN0-IV-83-16, Union Carbide Corporation (Gas Hills, WY) - Failure of Heap Leach Retention Pond.

ENCLOSURE D APR 2 21933

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

a. IE Infomation Notice 83-01, Supplement 1, Ray Miller, Inc., was issued on April 15, 1983 to all holders of a nuclear power reactor license or a construction pemit, nuclear fuel cycle licensees and Category B, Priority I material licensees.

b. IE Information Notice 83-21, Defective Emergency- Use Respirators was issued April 15, 1983 to all nuclear power reactor facilities holding an operating license or construction permit, research and test reactors, fuel cyle licensees, and Priority I material licensees.

4. Other Items

a. Quality Assurance Second quarterly report on the implementation of QA initiatives and the Ford Amendment (covering the period January 1- March 31, 1983) was fonarded to ED0 4/18/83.

b. As part of the Ford Amendment implementation, a fourth Case Study of existing QA systems was conducted the weeks of April 4 and 11 at the South Texas Project.

c. The utilities constructing the. Marble Hill and the Palo Verde units have agreed to participate in the independent audit portion of the Ford Amend-ment pilot program.

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APR 2 21983 ENCLOSURE D l

0FFICE OF NUCLEAR REGULATORY RESEARCH Items of Interest

' Week Ending April 22, 1983 l

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Semiscale

> Reanalysis of the feed and bleed test PL-3, using the upgraded models of the facility, is showing good code / experiment agreement. ,

The upgraded models treat the system heat losses and core power '

used to offset the heat losses mechanistically. This method, although costly to run, is necessary for the long duration transients now being run.

Preparations are continuing for an ATWS simulation, PL-7, in April.

The results of the Systems Operation Test, which tested the core power controller computer code, are being compared with the LOFT l

L9-4 ATWS test. The LOFT and Semiscale analysts are working closely i

to evaluate Semiscale's ability to perform a realistic ATWS test. ,

B&W Integral System Test Program Scaling experts from INEL,'BNL, ANL, MIT, Univ. of Md., B&W, and NRC met last week to discuss the scaling approach to be taken in 4

j designing the B&W test facility. Applying the results of the test orogram planned at the Univ. of Md. in conjunction with those of the f B&W facility is expected to provide a complete picture of the phenomena occurring in the B&W 2 X 4 design. The two organizations 4 Md. and B&W, will take different approaches to scaling. The short-fat approach at Md. and the tall-skinny approach at B&W will provide complete coverage of anticipated phenomena. As with all scaled test programs, the link with full-size plants will be '

through the advanced computer codes.

FLECHT SEASET The FLECHT SEASET Program Management Group (PMG) authorized Westinghouse to teardown the 163 Blocked Bundle Facility because no additional testing .is contemplated for this facility.

Code Assessment and Applications INEL has completed TRAC-PFl calculation of Semiscale Test S-NC-8B.

Assessment showed that TRAC-PF1 is capable of calculating natural circulation in single-phase, two-phase, and reflux codes. Report showing the results, EGG-NTAP-6210, has been published.

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ANL has completed RELAP5/ MOD 1 calculations for PKL Natural Circulation Tests, FLECHT SEASET Steam Generator Tests, and LOBI Tests. Reports '

showing the results for the first two have been published, NUREG/CR-3100 and NUREG/CR-2887. The LOBI report,which will have a restricted distribution because of the proprietary nature of data, is under i

publication. ENCLOSURE E APR 2 21953 -

4 BWR FIST ~

The natural circulation test series was successfully completed and data from these tests are available through the IHEL computer.

A small-break LOCA with HPCS failure test was also conducted on Thursday, April 14. Data from this test was available to NRC staff via the INEL computer on Monday morning, April 18. This demonstrates achievement of the rapid data reduction required for the fast test program currently planned.

The small-break test was terminated prior to completion by safety contro1g that had been administrative 1y set at a peak clad temperature of 1000 F. This temperature is significantly higher than pretest predictions and may be due to a change in the ADS flow area made in the facility after completion of the pretest prediction. Several options are now being considered by the PMG:

a. Accept the test and by post-test analysis see if TRAC predicts these higher temperatures,

b. Repeat the test with the temperature limit raised and run a post-test calculation, and

c. Repeat the test with the same ADS flow area as used in the pretest prediction.

PBF SFD-ST Neutron Tomographs

-The first prints of the tomographic reconstruction of neutron radiographs of the test section of the PBF Severe-Fuel-Damage Scoping Test (SFD-ST) have been made. Tomographic reconstruction (like a medical CAT scan) gives 2D cuts through a computer-constructed 3D image made from an array of neutron radiographs of the test object from different azimuths. The tomograph.ic images show a great amount of detail about the SFD-ST fuel debris, including the extensive relocation, before refreezing, of " liqui-fled fuel" (which is U02 dissolved in unoxidized liquid metallic Zircaloy),

The images are currently under detailed analysis at EG&G, but a set of prints is being sent to RES for examination here. .

TMI-2 Core Examination R. B. Foulds discussed DOE proposed meeting on TMI-2 Core Examination costs with F. Ross of DOE, April 19, pointing out that NRC staff is developing a prostective position for NRC prior to the meeting. Earliest possible date for DOE /NRC meeting on the subject now would be in the week of May 1, 1983. F. Ross will provide R. B. Foulds with some further

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clarification of costs with week. Ross indicated that EG&G/D0E is pre-paring 'a survey of industry labs as well as DOE labs that may become involved in the core examination and that DOE is hopeful that industry will also share some costs of the effort.

-APR 2 21983 ENCLOSURE E

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3-EPA Proposed Standards under Clean Air Act for Sources of Emissions of Radionuclides (40 CFR Part 61) "

On April 6, 1983, (48 FR 15076), the U. S. Environmental Protection Agency (EPA) publishedproposedstandardsundertheCleanAirAct(CAA)forsourcesofemissions of radionuclides (40 CFR Part 61) for (1) DOE facilities, (2) NRC licensed facilities (including Agreement States licensees)"and 6*on-DOE Federal facilities, (3) under e ground uranium mines; and (4) eleme.;tal hosphorus pl6nts. EPA chose not to prcpose standards for (1) coal-fired boilers, (2 the phosphate in'dustry. (3) other extraction industries, (4) uranium fual cycle facilitiec, dranium mill tailings, management of high-level waste, and (5) low energy acceTerators. The proposed standards for DOE facilities,sNRC and Agreement State lice s ed facilities, and non-DOE federal facil'1 ties s ara expressed in units of dosele@ivalent rate rather than emissions quantitles of radionuclides. '-

• The EPA proposed standard would specifically apply to'reslaiFeh and test readdors, hospitals, educational institutions, facilities in the radiopharmaceutical industry, and other similar facilitfits and activities licensed by the NRC and Agreement @tates.

Uranium fuel cycle facilities, now covered under EPA's 40 CFR Part 190 standards, would not be included under the CAA proposed standard, nor would uranium mi11' tailings (EPA's proposed 40 CFR Part 192 standards) or atmospheric releases in the management  :

of high-level waste (EPA's proposed 40 CFR 191 standards). The proposed standard for NRC and Agreement: State licensed facilities is a limit "of 10 mrem /yr to any, organ of any member of the public". The "stande.rds shall be implemented using p4 h-way and dose equivalent calculations based on EPA's codes AIRDOSE-EPA and d7 y RADRISK or modeling techniques which, in EPA's judgment, are as suitable for particular application as the EPA codes".

^N ie s

The proposed standard is likely to greatly impact not only on those NRC and Agreement State licensed facilities covered by the CAA but also would establish a precedent of

• a more restrictive standard than the present 40 CFR Part 190 or the existing 10 CFR Part 20 limits. Technical difficulties appear to exist in implementing such a low-level standard particularly 'when applied to any individual and afg organ; measurements to verify compliance appear impractical. In establishing the limit EPA has apparently chosen feasibility of attainment with existing controls of atmospheric releases as the.

single basis of selection of a numerical value. Note that a constant 10 mrem standard to all organs is inconsistent from a risk standpoint since all organs do not have the same sensitivity to radiation.

The NRC staff will testify in the EPA hearings, scheduled for April 28-30, 1983, and offer comments in opposition to the level proposed. Efforts are presently underway to conduct the necessary review of documents and to draft a staff position.

RES has been assigned the lead with expected assistance from NRR, NMSS, IE, SP, and ELD.

APR 2 21983 ENCLOSURE E'

t I

Severe Accident Analysis / Accident Sequence Evaluation Program AmeetingbetweenSevereAccidentAnalysis(SAA)programmanagers and Accident Sequence Evaluation Program (ASEP) managers was held on April 19, 1983 in Silver Spring, MD to discuss the possible interface and cooperation between the two programs in both the PWR and BWR areas. Representatives from Sandia National Lab., Idaho National Engineering Lab., NRC/RES/DRA and NRC/RES/DAE were present. ASEP identified dominant sequences for both PWR and BWR and <SAA is currently studying some of those programs which will bene-fit from this mutual cooperation.

Publications Issued _During the Week of April 18-22, 1983 NUREG-0961 "Long Range Research Plan; FY 1984-1988" Withdraw 0 of Regulatory Guide Regulatory Guide 1.67, " Installation of Overpressure Protection Devices",

has been withdrawn.

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A.?R S 2 1953 ENCLOSURE E

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OFFICE OF THE EXECUTIVE LEGAL DIRECTOR ITEMS OF INTEREST WEEK ENDING APRIL 22, 1983 1

Diablo Canyon Nuclear Power Plant, Units 1&2 In a Memorandum and Order issued on April 21, 1983, the Atomic Safety and Licensing Appeal Board granted the motion of the Joint Intervenors and the Governor of California to reopen the record in this operating license pro-ceeding to consider the , issue of design quality assurance. The Appeal Board concluded that it should preside over the reopened proceeding. The Appeal Board further ruled that "[f]ormal discovery on the issue of design quality assurance pursuant to the Commission's Rules of Practice shall begin immediately by'the Joir.t Intervenors and the Governor against the Applicant, and by the Applicant and the Staff against the Joint Intervenors and the Governor. Because the Staff has indicated discovery against it at this time will interfere with its review of the results of the Commission-ordered Independent Design Verification Program (IDVP), no discovery, pursuant to 10 CFR 2.744, will be< permitted against the Staff until further notice".

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• Shoreham Nuclear Power Station, Unit 1 s In a Memorandum a'nd Order issued on April 20, 1983, the Atomic Safety and i Li' censing. Board denied the moti'on of sintervenor Suffolk County to terminate the 'p'r esent operating license proceedirg. In its Order the Licensing Board ,

4 concluded "that under-the Commission's regulations and' applicable Federal

' statutes, an' applicant for 'an operating license should be permitted the 1,y opportunity to prove that the.. state of offsite emergency preparedness provides i .

reasonable assurance that adequate protective measures can and will be taken s.in the event of a' radiological emergency, even when a local county government fin the plume exposure pathway emergency planning zone declines either to

~ prepare or to implement a radiological emergency response plan". By a separate Order, the Licensing Board referred its decisi~on to the Atomic Safety and Licensing Appeal Board for review. j i, ,

APR S E 1933 ENCLOSURE F

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ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING APRIL 22, 1983 IAEA Technical Agsistance Visit From April 28 to May 6, Cecil Thomas, SSPB/NRR, will visit Colombo, Sri Lanka to assist the Sri Lankan Atomic Energy Authority in preparing a report on the technical and environmental considerations of a Triga reactor for Sri Lanka. The Sri Lankan government is interested in acquiring a Triga reactor for training and research.

International Visitors During this week Mr. Ronald Potter and Dr. Paul D. Parsons of the UK Atomic Energy Authority (AEA) attended the PBF Review Meeting and discussed the severe fuel damage program at INEL.

During this week and next Monday, Ors. Siegfried Hagen and Peter Hofmann and Mr. Albert Friege of the German government research center at Karlsruhe attended the PBF Review Meeting at INEL and discussed severe fuel damage investigations at SNL.

On Thursday and Friday Mr. Guenter Langer of the Battelle Research Laboratory in Frankfurt, Germany toured SNL and discussed hydrogen control research.

Foreign Trip Reports William T. Russell, Chief, Systematic Evaluation Progrcm Branch, DL March 22-25,1983, Visit to Spain _:

Mr. Russell participated in a series of meetings on the Spanish SEP Program and the operating history of both Zorita and Garona. He also l

l presented a briefing on the status of SEP Phase II in the U.S.

T. S. Kress, NRC/DAE Program Manager at ORNL March 21-25.1983, Visit to Paris, France:

At the request of the USNRC, Mr. Kress attended the final meeting of the CSNI-sponsored Group of Experts on Nuclear Aerosols. He attended t

the inaugural meeting of the new CSNI Group of Experts on Source Terms.

l APR 2 21933 ENCLOSURE G i

OFFICE OF STATE PROGRAMS ITEMS OF INTEREST W EK ENDING APRIL 22, 1983 Teletherapy Course On April 27-29, 1983 twelve Agreement State inspectors will attend the Cobalt Teletheraphy Calibration course at M. D. Anderson Hospital in Houston, Texas.

APR 2 21933 ENCLOSURE H' f -

0FFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA ITEM OF INTEREST WEEK ENDING APRIL 22, 1983 The Potential for Water Hammer During the Restart of RHR Pumps at BWR Nuclear Power Plants, AEOD/E309 An AE0D engineering evaluation was issued on April 21, 1983 describing a situation in which a momentary power interruption to operating BWR RHR system pumps, while mitigating the consequences of a postulated LOCA, might cause water hammer damage to the system equipment. The report points out that vertical piping runs,. coupled with a lack of back flow protection devices in portions of the system, would allow draindown and void formation during pump cooldown which could be followed by a water hammer during pump restart.

The report concluded that procedure development and operator awareness would be adequate to address this matter. The report was transmitted to NRR for possible input in the task to resolve Unresolved Safety Issue A-1, Water Hammer.

ENCLOSURE J APR 2 21983

6 1TEMS ADDRESSED BY THE COMMISSION - WEEK ENDING APRIL 22, BS3 A. STAFF REQUIREMENTS - BRIEFING ON SECY-83 PROPOSED REVISION TO 10 CFR PART 35 " HUMAN USE OF BYPRODUCT MATERIAL," 10:00 A.M., TUESDAY, APRIL 19, 1983, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE),

Memo SECY to Dircks, 4/19/83 The Commission was briefed by staff on the proposed revisions to the rules covering licensing of byproduct material.

The Commission also heard from the following:

1. William Spell, representing Agreement States

2. Dr. Ralph Robinson, President, American College of Nuclear Physicians

3. Otha W. Linton, American College of Radiologists

4. NMSS staff members P. Vacca and J. DelMedico The Commission. requested:

1. That staff submit current estimates on such information as the number of applications by type, work factors, and numbers pending; and (NMSS) (SECY Suspense: to be determined)

2. That P. Vacca and J. DelMedico mark up the staff proposal with changes to reflect what would satisfy their concerns.

(NMSS) (SECY Suspense: to be determined)

The Chairman asked that Commissioners give guidance to staff -

on the proposed procedures by notation votes.

B. STAFF REQUIREMENTS - BRIEFING ON SYSTEMS INTERACTION, 2:00 P.M., MONDAY, APRIL 18, 1983, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE), Memo SECY for the Record, 4/19/83 The Commission was briefed by the staff on the systems interaction program and on the status of USI A-17.

The Commission took no action and made no requests of the staff.

'E ENCLOSURE 0-

ITEMS' ADDRESSED BY THE COMMISSION - WEEK ENDING APRIL 22, 1983 C. STAFF REQUIREMENTS - DISCUSSION OF REGULATORY REFORM TASK FORCE -

ADMINISTPATIVE PROPOSALS BACKFIT RULF, 2:00 P.M., THURSDAY, APRIL 14, 1983, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC XTTENDANCE), Memo SECY for the Record, 4/19/83 The Commission met to consider the revised draft staff require-ments memorandum circulated by the Task Force Chairman on April 12, 1983, concerning administration of backfit decisions and the Commission's'backfit rule, 10 CFR 50.109.

Commissioner Asselstine indicated he would shortly circulate a revision of the draft SRM.

The Commission took no action at this meeting.

D. STAFF REQUIREMENTS - BRIEFING ON SALEM, 9:30 A.M., WEDNESDAY, APRIL 20, 1983, COMMISSIONERS' CONFERENCE ROOM, (OPEN TO PUBLIC ATTENDANCE), Memo SECY for the Record, 4/20/83 The Commiss' ion met to' hear statements from officers of Public Service Electric and Gas Company regarding recent events at Salem. Present were:

1. Robert I. Smith, Chairman of the Board and CEO

2. Richard A. Uderitz,.'Vice President-Nuclear

, 3. Henry Miruda,. General Manager, Nuclear Services

4. John-Zupko, General Manager, Salem Operations

5. John Boettger,' General Manager, Nuclear Support .

There were no requests made at the meeting.

E. STAFFREQUIREMENTS-DISdJSSION/F0SSIBLEVOTEONRESTARTOFSALEMUNITS1 AND 2, 9:30 A.M., THUR50AV, APRIL 14, 1983, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO Pl:BLIC ATTENDANCE), v.emo SECY to Dircks, 4/22/03 The Commission was briefed ori the rEsults of the staff's review of the February 22 and 25 incidents at Salem Unit 1.

A majority of the Commission (Commissioners Gilinsky, Ahearne and Asselstine) preferred to meet on possible enforcement action before voting on restart, e

i Commissioner Ahearne requested that the staff provide a program for checking the status of license commitments regarding operator testing and training.

> (subsequently, a briefing on possible enforcement action was scheduled for April 20 and a followup restart briefing for April 26.)

ENCLOSURE 0 ggg

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• NRR MEETING NOTICES

• APRIL 22,1983 DOCKET APPLICANT /

LOCATION PURPOSE ATTENDEES NRR CONTACT DATE/ TIME NUMBER 50-261 P-422 To discuss licensing organization, Carolina Power & Light G. Requa 4/25/83 D0:00 am Bethesda management and scheduling of (H.B. Robinson 2) licensing open items STN 50-546 P-110 To discuss issues related to Public Service of Indiana P. O'Connor O/26/03 10:00 am STN 50-547 Bethesda - operating license review of Marble Hill 1 A 2) 50-440 Perry Site To discuss NRC regional staff inspec- Cleveland Elec. Ill. Co. J. Stefano d/26/83

@:00 am 50-441 Perry, Ohio tion findings of containment GAI structure weld deficiencies in the suppression pool / annulus area

4/26/83 50-29 P-114 To discuss YAEC's request for relief Yankee Atomic Elec. Co. J. Lyons 9

00 am Bethesda from installation of a Reactor (Yankee)

Vessel Water Level System 50-397 WNP-2 Site Instrumentation and Control System Washington Public Power R. Auluck

4/26-28 Supply System 8:30 am Richland, WA Branch Site-visit h!

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PLEASE BE ADVISED THAT DAILY RECORDINGS CAN BE HEARD ON 492-7166 0 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.

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$5 DO to NRR MEETING NOTICES

• DOCKET APPLICANT /

PURPOSE ATTENDEES NRR CONTACT DATE/ TIME NUMBER LOCATION P-ll8 To provide guidance for regional NRC Region Coordinators P. Erickson' 4/27/83 9:00 am Bethesda review of proposed TS's for NUREG-0737 items identified in Generic Letter 82-16 P-110 To discuss proposed decontamination Northeast Nuclear Energy Co. P. Leech I4/27/83 9:30 am Bethesda of steam generator primary channel (Millstone 2) heads 50-382 Waterford Site Assess status of construction and Louisiana Power & Light J. Wilson 4/27-29/83

9:00 am St. Charles Parish, completion schedules for Waterford 3 Louisiana 50-220 MNBB-1713 Discuss review of masonry walls at Niagara Mohawk Power Corp. R. Hermann 4/27/83

9:30 am Bethesda Nine Mile Point 1 50-461 AR-2242 Clinton - Discussion of Outstanding Illinois Power Co. H. Abelson 4/28/83 1:00 pm I,ethesda Issue No. 3: Seismic Analysis 50-395 MNBC-6507 To discuss licensee's submittal of South Carolina Elec. & J. Hopkins

'4/28/83 9:00 am Bethesda February 1,1983, concerning their Gas Co.

Seismic Confirmatory Program 4/28/83 50-458 MNBB-1713 To discuss River Bend Station Gulf States Utilities E. Weinkam

.9:00 am Bethesda Preoperational Environmental t Monitoring Program 9

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E b5 PLEASE BE ADVISED THAT DAILY RECORDINGS CAN BE HEARD ON 492-7166 v

• 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.

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bD as NRR MEETING HOTICES*

TL DOCKET APPLICANT /

LOCATION PURPOSE ATTENDEES NRR CONTACT

, DATE/ TIME NUMBER 50-219 P-118 To discuss status of existing core GPU Nuclear Corp. J. Lombardc 4/28/83 (0yster Creek)

, 9:00 am Bethesda spray sparger with relation to core l

spray distribution and sparger inspection results STN 50-454 P-114 -

To appeal Standard Tech Spec require- Commonwealth Edison L. 01shan

'-4/28/83 (Byron)

, 9:00 am Bethesda ment that safety-related equipment can be out of service for only 72 hrs.

j 50-410 P-110 To discuss plans for review of the Niagara Mohawk Power Corp. M. Haughey 4/28/83 i 1:00 pm BethesdG Operating License application for Nine Mile Point 2 50-388 P-114 To discuss audits and reviews of Pennsylvania Power & Light R. Perch 5/3/83 1:30 pm Bethesda Susquehanna 2 activities confirming Unit 2 design adequacy 50-254/265 P-114 To receive the CECO presentation on Commonwealth Edison Co. R. Bevan 5/3/83 10:00 am Bethasda the technical and legal basis for use of their Economic Generation Control 4 systems at Dresden, Quad Cities, Zion and LaSalle Stations.

STN 50-454 P-110 To present background information on Commonwealth Edison Co. L. 01shan 5/4/83

1

00 pm STN 50-455 Bethesda the Byron design verification program m

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,3 PLEASE BE ADVISED THAT DAILY RECORDINGS CAN BE HEARD ON 492-7166 i

CCopies 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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20 NRR MEETING NOTICES

• as 2 APPLICANT /

DOCKET PURPOSE ATTENDEES NRR CONTACT DATE/ TIME NUMBER LOCATION To discuss proposed sleeving of Northeast Nuclear Energy P. Leech 5/4/83 P-114 .

4 9:30 am Bethesda steam generator tubes-Millstone 2 To discuss improvements in General General Electric D. Fieno 5'/5/83 P-110 9:00 am Bethesda- Electric physics methods and the submittal of topical reports 4

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• 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.

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NMSS MEETING NOTICES 98 FOR WEEK ENDING: 4/22/83 to Page 1 Divisien of Funi Cycle and Material Safety to rd DOCKET ATTENDEES /

83 NRC CONTACT NUMBER LOCATION PURPOSE APPLICANT DATE/ TIME V. Miller (FC)

Mtg with the Deputy for Environ- V. Miller 4/21/83 Pentagon mental and Safety, Office of R. E. Cunningham (FC)

Assistant Secretary of the Air Force to review the progress of the proposed broad specific license for the Air Force.

To discuss proposed NRC, EPA MOU R. G. Page (FC) R. G. Page 4/21/83 Crystal City, VA on control of areas contaminated G. Burley (EPA) 9:00am with radioactive baterials Willste Discuss IE Bulletin 83-10. R. Odegaarden (FC) R. Odegaarde'n 4/22/83 C. MacDonald (FC) 9-12:00 Les Poppe + 2 (Chem-Nuclear)

To observe ORAU psrform a con- A. L. Soong (FC) A. L. Soong 4/25-29/S3 70-620 Wood River Junction, RI firmatory survey ofliNC facility.

Chicago, IL To attend American Ceramic Society R. D. Hurt (FC) R. D. Hurt 4/25-27/83 Project M-32

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Meeting session (Papers on issues R. C. Mairson (DOE) related to West Valley Waste W. H. Hannum (DOE)

Solidifcation Project)

Project Willste To discuss dry cask storage ISFSI L. C. Rouse (FC) J. P. Roberts 4/27/83 J. P. Roberts (FC) 1:00pm M-33 Topical Report with Ridihalgh, Eggers, and Associates (REA). N. Davison (FC)

Phil Eggers (REA)

Chicago, IL To meet with Region III personnel L. C. Rouse (FC) L. C. Rouse 4/27-28/83 to discuss transfer of licensing R. G. Page (FC) m functions.

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45 NMSS MEETH.G NOTICES

" FOR WEEK ENDING: 4/22/83- -

Divisien of Fu11' Cycle and Mat

• rial Safety Pagm 2 I'3 DOCKET ATTENDEES /

h$ NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT UATE/ TIME N. Bassin Parsippany, Review of the new irradiator N. Bassin (FC) 4/27-28/83 licensing guide with industry G. Dietz (Isomedix)

NJ representatives. G. Keller (Becton-Dickinson)

Chicago, IL To review final environmental W. A. Nixon (FC) W. A. Nixon 4/27-29/83 40-2061 statement for decommissioning Kerr-McGee Rare Earths facility.

R. Odegaarden (FC) R. Odegaarden

'5/2 71-6639 Willste MH-1A C. MacDonald (FC) j 1-5:00 H. Lake (FC)

W. Lee (FC)

j. A. Trujillo, R. Pope (Sandia)

H. Young, E. Barraglach, l B. Smith (DOE) i H. Crawford, R. Eggers (REA)

To discuss contamination at W. R. W. T. Crow (FC) W. T. Crow 5/3/83 40-86 Willste Reps fm W. R. Grace 10:00am Grace site Pompthn Plains, NJ.

Gore, OK To accompany ORNL' environmental E. Y. Shum (FC) ~ E. Y.'Shum 5/3-5/6/83 40-8027 M. Rhodes team to conduct site visit at

' Kerr-McGee facility.

West Valley, To discuss seismic design basis A. T. Clark (FC) A. T. Clark 5/5/83 Project M-32 NY at West Valley. W. Burkhardt (FC)

R. Hurt (FC)

W. Hannum (DOE)

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• to HMSS MEETING !!0TICES April 22.1983 ,

"* Division of Waste Management '

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" DOCKET ATTENDEES /

NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT DATE/ilME 5/2-4/83 Ft. Mitchell, KY EPA Symposium on Land R. Pennifill, WMLL R. Pennifill, .

Disposal of Hazardous WMLL Waste

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April 22, 1983 NMSS Meeting Notices Division of Safeguards ATTENDEES /

DOCKET PURPOSE APPLICANT NRC CONTACT DATE/ TIME NUMBER LOCATION Raleigh, N.C. Shearon Harris Hearing D. A. Kers D. A. Kers 4/25-27/83 50-400 (Shearon Harris) witness depositidn Savannah, GA To present three speeches G. W. McCorkle G. W. McCorkle 4/25-27/83 -

at the ANS Conference.

1. Insider Rule

2. Threat Assessment

3. Regulatory Effective-m

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, April 22, 1983 E .. -

% IE HEEllHG HOTICES l3 DOCKET ATTENDEES /

DATE/IIHE NUlBER LOCAT10N PURPOSE APPLICANT .HRC CONTACT 4/25/83 -

Cincinnati,0ll Attend public meeting on J. H. Sniezek, IE J.11. Sniezek Zimmer 4/25-26/83 PNL, llanford Finalize work phase review E. H. Brach, IE E. W. Brach of non-NRC QA Programs Contractor Personnel 4/26/83 50-324 Southford, NC Enforcement Meeting J. Axelrad, IE J. Axelrad 325 Brunswick 5/2-5 Midland, MI Provide testimony at ASLB J. Gilray., IE J. Gilray Court House hearings on QA implementation Bechtel 5/3-5 Santa Cruz, CA IEEE-P934 Subcommittee on 11. Belke, IE W. Belke spare parts P

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• RES MEETING NOTICES- April 22, 1983 - .

w ATTENDEES / NRC CONTACT LOCATION PURPOSE DATE/ TIME DOCKET APPLICANT NUMBER (IfApplicable) then, Rhee, Shotkin, Sullivan Rhee' Germany 2D/3D Coordination Mtgs April 25-29 Landry Landry Idaho Falls, ID Semiscale April 25-29 Shotkin Shotkin, Odar, Beckner i

Rm. 1224 ROSA-III Calculation April 29 w/ TRAC-BD1 and Test Plans 10:30 for the 180 Sector Sullivan Rm.1133 20/3D i April* 29 .

9:00 '

1 EPA hearings on Radiation W. A. Mills W. A. Mills GSA Auditorium i 4/28-30 18th & F St., NW Standards under the Clean 9 a.m. Wash., DC Air Act Task Analysis peer review GPC staff, J. Jenkins

, 04/ 2W83 Columbia, MD Biotechnology staff, HFSB staff Discuss progress and problems J. Defield, H. Ettinger, L. Hendricks Los Alan.os, NM G. Wood, B. Skaggs, 04/25-04/27 with technical assistance contracts C. Fairchild, LANL; A7005 and A7039, to quantify and imnrove the nrotection provided L. Hendricks E by respiratory protective equin- .

P ment against airborne-fedioactive 8 material 04/25-28/83 Gatlinburg, TN Fifth Training Symposia J. Lowry J. Lowry

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'* RES MEETING HOTICES April 22,1933 .,

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$ ATTENDEES / NRC CONTACT PURPOSE <

DOCKET LOCATION APPLICANT DATE/ TIME NUMBER (If Applicable)

IAEA Senior Advisory Group Mtg. SAG Members R.B. Minogue Vienna, Austria 4/25-29 D. F. Ross R.B. Minogue 1140-SS Courtesy call by Mr. S. Park, 5/3 Scientific Attache of the R. B. Minogue 9:30 AM Embassy of Korea in Washington Meeting with EPA staff regarding Mr. Sjoblom (EPA) D.F Ross 4/27 EPA Offices F. Arsenault, NRC Crystal City Mall deconmissioning 2:00 PM , W. Mills, NRC D. F. Ross, NRC K. Steyer, NRC G. Arlotto, NRC Idaho Falls, ID SFD Foreign Participants Meeting 4/18-4/22 and the running of the second Silberberg/ Van Houten/

PBF Test Wright /Jankowski G. Marino Marino Bassett ACRS Class 9 Subcommittee Meeting 4/26 H-Street 9

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April 22,- 1983

.(( REGION ! MEETING NOTICES , ,

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ATTENDEES /

DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT 5/2/83 50-352 Philadelphia, PA To present the results Philadelphia L. E. Tripp 50-353 of the Systematic Electric Co. '-

Assessment of Licensee '

Performance (SALP) for Limerick Generating Station, Unit 1

. 5/4/83 50-322 Region I Office Shoreham SALP Long Island R. M. Gallo Lighting Co.

5/5/83 50-24/ Region I Office Indian Point Unit 2 Consolidated H. B. Kister SALP Edison Co. of New York, Inc.

5/10/83 50-293 Boston, Mass. Management Meeting to Boston Edison Co. T. C. Elsasser Discuss Performance -

Improvement Program at Pilgrim .,

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April 22, 1983 .

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RII MELT!Ng NOTICE

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DOCKET NRC CONTACT Pt!RPOSE ATTENDEES /APPLICAtlT JATE/ TIME, iPJMBER LOCATION Licensee, Deputy Regional R. Lewis Brunswick Site Enforcement ' Conference

)4/26/83 Carolina Power & Light Administrator and Selected 3:00 a.m. Southport, NC Company - Brunswick RII Staf f Members Facility Regional Administrator, M. Sinkule 34/27/83 RIl Office South Carolina Electric and Gas Company - SALP Selected RII Staff Members.

9:30 a.a. Board Meeting ard HRR Representative Babcock and Wilcox Company, Licensee, Regional P. Stohr 04/28/83 RII Office Administrator and Selected 8:30 a.m. Commerical Nuclear Fuel Plant, meeting to discuss RII Staff Members regulatory requirements for nondestructive assay systems Meeting with Florida Power Licensee, Regional R. Lewis 04/28/33 RII Office Arministrator and Selected and Light Company to discuss 00:00 a.m. Region II Staff Members Turkey Point Auxiliary feedwater issue Carolina Power & Light Licensee, Regional M. Sinble 15/10/83 Corporate Office Raleigh, NC Company SALP 11eeting - Administrator and Selected 1:30 p.m. RII Staff Members Brunswick, Robinson and Ifarris Silas Quarterly Regional Resident Inspectors, Selected R. Lewis 05/11/83 RJI Office Resident Inspector Meeting RII and llQs Personnel 8:00 a.m.

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