ML20134L928

Weekly Info Rept for Wk Ending 850823

ML20134L928
Person / Time
Issue date:	08/29/1985
From:	Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To:
References
WIR-850823, NUDOCS 8509030472
Download: ML20134L928 (52)

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% P b fL August 29, 1985 For: The Commissioners From: T. A. Rehm, Assistant for Operations, Office of the ED0

Subject:

WEEKLY INFORMATION REPORT - WEEK ENDING AUGUST 23, 1985 A summary of key events is included as a convenience to those Commissioners who may prefer a condensed version of this report.

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

International Programs G State Programs H Resource Management I*

Analysis and Evaluation of Operational Data J Small & Disadvantaged Business Utilization & Civil Rights K Regional Offices L*

CRGR Monthly Report M Executive Director for Operations ,

N*

Items Addressed by the Commission 0 Meeting Notices P Proprietary or Other Sensitive Information (Not for Q external distribution)

• No input this week, hDR' hh hp C J WEEMLymy OREPT PDR T/ A. Rehm, Asbtant for Operations Office of the Executive Director for Operations

Contact:

T. A. Rehm, EDO 492-7781

t HIGHLIGHTS OF WEEKLY INFORMATION REPORT WEEK ENDING AUGUST 23, 1985 Shoreham On August 15, 1985, at 8:40 pm, the Shoreham Plant was raising reactor power to about 2.5% to perform HPCI testing when one of the turbine bypass valves started to oscillate, causing a spike in reactor power. The licensee attempted to control the oscillation by adjusting the reactor pressure regulator, but two more oscillations occurred. The last one caused a power spike to approximately 5.5% power. The licensee has suspended testing until it can investigate the cause of the oscillations and correct it.

Meeting with the State of Virginia On August 21, 1985, OSP and Region II staff members met with the Assistant Health Commissioner and staff in Richmond, Virginia. The State indicated its intention to proceed with full Agreement State status with NRC (excluding regulation of uranium milling) and also discussed its desire to enter into an MOU regarding inspection of low-level radioactive waste packaging and transportation at NRC licensed facilities.

Public Service Electric and Gas Company On August 21, 1985, Public Service Electric and Gas Company was issued Materials License No. SNM-1953 for Hope Creek Generating Station, authorizing the receipt, possession, inspection, and storage of uranium enriched in the U-235 isotope contained in fuel assemblies in their shipping containers and spent fuel pool.

Readiness Review Program On August 19-20, 1985, the Chief, Quality Assurance Branch, Division of Quality Assurance, Vendor, and Technical Training Programs parti-cipated in a meeting with Region II and NRR in Atlanta, GA to discuss lessons learned from NRC review of Module One of the Readiness Review Program so as to improve the review process for future modules, i

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l AUG 2 ? 1985 ,

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0FFICE OF ADMINISTRATION Week Ending August 23, 1985 ADMINISTRATION OF THE FREEDOM 0F INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Carryovers, 1984 179 23 Received, 1985 588 33 Granted 460 25 Denied 126 13 Pending 181 18 ACTIONS THIS WEEK Received Rod Buckles, Requests data regarding nuclear power plant declarations NUS Corporation of " unusual events" and " alerts" in 1984.

(85-576) .

Steven Aftergood, Requests copies of " Review of NRC's Reactor Safeguards Committee to Program" and " Follow-Up on OIA Report ' Review of NRC's Bridge the Gap Reactor Safeguards Program'".

(85-577)

Vincent J. Kiernan, Requests a copy of F0IA-80-589 from John Vail regarding The Herald Nuclear Fuel Services of Erwin, Texas.

(85-578)

Steven Aftergood, Requests all records regarding a meeting in February 1985 Committee to between representatives of the Israeli Atomic Energy Bridge the Gap Comission and NRC's RES, IP, NRR and IE offices.

(85-579) .

David A. Repka, Requests records reflecting the NRC's current policy and Bishop Liberman, criteria for determining when individuals and Cook, Purcell organizations requesting data under the F0IA are not

& Reynolds required to pay fees for NRC processing of a request.

(85-580)

Bruce W. Stainbrook, Requests a copy of the license for American Micro Scan BBL Microbiology of Mahevah, New Jersey.

Systems (85-581)

CONTACT: J. M. Felton 492-7211 ENCLOSURE A Atle ? 31995

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Received, Cont'd Stephen H. Hanauer, Requests copies of Power Plant Examinations Results Technical Analysis Sumary Sheets for certain reactor operator and senior Corporation reactor operator examinations of 12 specified (85-582) plants.

Donald Pay, Requests records regarding low-level radioactive waste Technical disposal in South Dakota and agreement state status Information Project for South Dakota.

(85-583)

Albert V. Carr, Requests records related to Enforcement Action EA 84-93 Duke Power Company being taken against Duke Power Company (Catawba nuclear (85-584) power plant).

Stephanie Dematitis, Requests records regarding NRC's data processing Data Base Inc. centers.

(85-585)

Kay L. Dove Requests a copy of SECY-85-65 and any related records.

(85-586)

Steven Aftergood, Requests four categories of records regarding the Comittee to University of Michigan Ford nuclear reactor and its Bridge the Gap conversion from highly enriched uranium (HEU) fuel to (85-587) low enriched uranium (LEU) fuel.

Sandra Swan Travis, Requests copies of quotations from respondents to Data Services RFQ No. 503155 issued on February 21, 1985, for storage (85-588) space at the environmental secure storage facility in the Washington, DC, area.

Jay E. Silberg, APPEAL TO THE COMMISSION for the release of the denied Shaw, Pittman, portions of SECY-85-80.

Potts & Trowbridge (85-A-33-85-493)

Granted ,

T.F. Sheehan, In response to a request for a copy of the contract Gilbert / and nonproprietary version of the proposal related to Comonwealth, Inc. RFP RS-0RM-85-312 entitled, " Lease of a Data Base (85-218) Management System and Supporting Integrated Software Packages," made available a copy of the requested proposal. Informed the requester that the contract is already available at the PDR.

Jim Pedro, In response to a request for five specified sumaries NUS Corporation of the IDCOR/NRC Technical Exchange Meetings, made (85-465) available three meeting sumaries. Informed the requester that meeting sumaries for two meetings could not be found.

ENCLOSURE A RUG i 31%$

3 Granted, Cont'd Steven Fagan, In response to a request for a copy of a completed Fort Worth Star- NPC staff report on Region IV management decisions Telegram regarding the March 8, 1984, "T-shirt incident" at the (85-477) Comanche Peak nuclear power plant, informed the requester that there is no completed report subject to this request.

Linda Smith, In response to a request for a copy of SECY-84-13B, S. Levy made available a copy of the requested paper.

Incorporated (85-507)

Lyle Graber, In response to a request for copies of NUREG/CR-0073 NUS Corporation and SECY-85-30, made available a copy of NUREG/BR-(85-508) 0073 entitled, " Project Managers Handbook". Informed the requester that the disclosed portions of SECY-85-60 are already available at the PDR.

(Individuals In response to a request for copies of records pertaining to exposure to radiation in 1984 at the St.

requesting information ) John's Regional Health Center in Missouri, made *

(85-557) available five records.

Vincent Clark, In response to a request for copies of licenses issued Delta Lighting to Stocker and Yale, Inco.porated, made available 14 Corporation records.

(85-558)

Richard A. Sloan, In response to a referral from the D0J of one record Phillip C. relating to the industrial gas industry, made available Goldstick & a copy of the record.

Associates, Ltd.

(85-565)

Ophelia G. Williams, In response to a request for biographical information J/R/A Associates pertaining to an NRC employee, made available a copy (85-571) of the requested record. -

Ellyn R. Weiss, In response to a request for a copy of an ACRS letter to Union of Concerned the Comission on July 17, 1985, on the ACRS position en Scientists Commission's policy on safety goals, made available a (85-572) copy of the requested record.

Vincent J. Kiernan, In response to a request for a copy of F01A-80-589 from The Herald John Vail, made available a copy of the FOIA request.

(85-578)

ENCLOSURE A

$UG 2 3

4 Denied Nina Bell, In response to a request for all records relating to Nuclear Information the receipt, analysis and denial of one or more "Show and Resource Service Cause" petitions filed by Cynthia Stewart on behalf of (84-665) Jacksonians for Livable Energy Policies (JULEP) requesting actions on the Grand Gulf nuclear power plant, made available 22 records. Informed the requester that additional records subject to this request are already available at the PDR. Denied one record in its entirety compiled for law enforcement purposes. Denied portions of one record compiled for law enforcement purposes and release of which would tend to inhibit the open and frank exchange of ideas essential to the deliberative  ;

process. Denied portions of one record, release of which would tend to inhibit the open and frank exchange of ideas essential to the deliberative process.

Lynn Cunningham, In response to a request for copies of records written or The Times- received by the NRC subsequent to the December 31, 1984, i Picayune OIA report on Region II and the Grand Gulf nuclear power Publishing Corp. plant, made available one record. Denied 29 records in (85-197) their entirety, release of which would interfere with ongoing investigations on Grand Gulf. Denied nine i records in their entirety, release of which would tend to inhibit the open and frank exchange of ideas essential to the deliberative process.

Sylvia Tognetti, In response to a request for copies of (a) connents of Christic Institute the Connissioners in providing guidance to the staff on (85-456) developing recommendations to Congress for legislative i measures in response to the Supreme Court decision in Silkwood v. Kerr-McGee Cor)., and the Connission staff ,

comments in response to SE;Y-84-146A, and (b)

~

recommendations and proposed legislation prepared by the l Office of the General Counsel for presentation to the <

99th Congress in response to the Supreme Court Silkwood decision and on the subject of punitive damages, made available two records. Denied six records in their c entirety, release of which would tend to inhibit the open and frank exchange of ideas essential to the deliberative process.

Jim Thomas, In response to a request for records between officials  !

NTEU President in the Division of Facilities and Operations Support and '

(85-509) officials in the Division of Security relating to theft of NRC equipment, denied in their entirety, three records '

containing information which constitutes advice, opinions, and recommendations. ,

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ENCLOSURE A

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Denied, Cont'd Robert T. Simmons In response to a request for biographical data on an (85-516) NRC employee and Systematic Assessment of Licensee Performance (SALP) reports for ten plants, made available two records. Informed the requester that additional ? cords subject to this request are already available tt the PDR. Denied portions of one record, release of which would constitute a clearly unwarranted invasion of personal privacy.

Lyle Graber, In response to a request for a copy of SECY-85-209, NUS Corporation denied this pater in its entirety, release of which (85-523) would tend to inhibit the open and frank exchange of ideas essential to the deliberative process.

l ENCLOSURE A AUG 2 31985

i WEEKLY INFORMATION REPORT DIVISION OF CONTRACTS WEEK ENDING AUGUST 23, 1985 IFB ISSUED I FB No . : RS-0RM-85-334

Title:

"On-Call Maintenance for Microcomputers and Related Equipment"

Description:

On-call maintenance including all necessary maintenance labor, documentation, repair parts, supplies, tools, test equipment, transportation and their related services for NRC microcomputers and related equipment.

Period of Performance: 2 years Sponsor: Office of Resource Management Status: IFB issued on August 21,1985. Bids due on September 19, 1985.

RFP ISSUED RFP No.: RS-01E-85-167

Title:

" General Course in Non-Destructive Examination Technology and Codes"

Description:

The purpose of this project is to provide NRC personnel the detailed technical training.in nondestructive examination (NDE) and the applicable codes necessary to enable them to conduct in-depth inspection of NRC licensed facilities under construction or modification to determine whether or not such facilities and components are constructed properly in accordance with applicable codes and standards.

Period of Performance: 3 years Sponsor: Office of Inspection and Enforcement i Status: RFP issued on August 16, 1985. Proposals due September 16, 1985.

RFP No.: RS-0IE-86-170 Titl e: " Technical Assistance for Emergency Response"

Description:

The purpose of this project is to provide technical, logistical and administrative assistance for the maintenance and functioning of the NRC Headquarters Operations Center. The contractor shall provide technical, logistical and administrative support to the NRC's Headquarters Operations Center to fulfill exercise requirements and meet unanticipated needs that arise during normal operation or during an incident within a very short time span.

Period of Performance: 1 year with two one-year options.

Sponsor: Office of Inspection and Enforcement Status: RFP issued on August 20, 1985. Proposals due September 20, 1985.

ENCLOSURE A AUG 2 31985

9 Division of Contracts Weekly Information Report PROPOSALS UNDER EVALUATION RFP No.: ADM-85-235

Title:

"NRC Translation Services"

Description:

The contractor will be required to furnish translation services for reports and other related material provided by NRC when issued by a formal work order.

Period of Performance: 2 years Sponsor: Office of Administration Status: RFP closed on August 19, 1985. Proposals forwarded to Source Evaluation Panel for review on August 20, 1985.

RFP No. : RS-NMS-85-008

Title:

" Technical Assistance in Hydrogeology - Project A - Testing"

Description:

The contractor shall provide technical assistance to the NRC in its review of DOE site investigations for a potential high level waste geologic repository.

Period of Perfonnance: 2 years with 3 one-year options.

Sponsor: Office of Nuclear Material Safety and Safeguards Status: Negotiations completed on August 21, 1985. Best and Final offers are due on August 26, 1985.

RFP No.: RS-NRR-85-054

Title:

" Development of an NRC Simulation Facility Evaluation Program"

Description:

The contract objectives are to develop, refine and validate criteria and methodology for the review of nuclear power plant simulation facilities; recommend size and make-up of a review team; and develop a schedule for conduct of review. Work will include a review of applicable literature; development of a methodology; testing this methodology through conduct of actual simulation facility reviews and preparation of detailed recommendations.

Period of Performance: 14 months with an option for an additional 6 months.

Sponsor: Office of Nuclear Reactor Regulation

~ Status: Best and Final offers received on August 19, 1985 and forwarded to Source Evaluators for review on August 19, 1985. -

CONTRACTS AWARDED I FB No. : NRC-10-85-252

Title:

"Micrographic Services of Source Drawing Documents"

Description:

The contractor shall provide services to the U.S. Nuclear Regulatory Commission to produce microfiche from source documents provided.

Period of Performance: 24 months Sponsor: Office of Administration Status: Fixed Price Requirements contract awarded to Microform, Inc. in the estimated amount of $165,475.00 on August 22, 1985.

ENCLOSURE A AUG 2 31985

l Division of Contracts Weekly Information Report CONTRACTS AWARDED (cont'd)

I FB No . : RS-ASB-85-401

Title:

" Stenographic Reporting Services"

Description:

Provide stenographic reporting services outside and inside the Washington, D.C. Metropolitan Area (excluding NRC Commission meetings held in the D.C. area).

Period of Performance: 2 years Sponsor: Atomic Safety and Licensing Board Panel Status: Fixed Price Requirements contract awarded to Ace-Federal Reporters, Inc. in the estimated amount of $1,388,848.00 effective August 16, 1985, outside D.C. and October 1,1985, inside D.C.

RFP No.: NRC-02-85-002

Title:

" Technical Assistance for Design Reviews of High Level Nuclear Waste Geologic Repositories"

Description:

The contractor shall be required to provide support services, including analyses, computations, engineering evaluations, citations to literature, and documentation thereof to assist the NRC to review, evaluate, and comment on the design of a geologic repository contained in the U.S. Department of Energy's (D0E) site characterization plans (SCP).

Period of Performance: 3 years Sponsor: Office of Nuclear Material Safety and Safeguards Status: Cost-Plus-Fixed-Fee contract awarded to Itssca Consulting Group, Inc. in the estimated amount of $1,417,252.46 effective August 22, 1985.

ADMINISTRATIVE MATTERS

1. The protest filed by Software AG of North America on July 17, 1985, against award of Contract No. NRC-33-85-312 to Cullinet Software, Inc.

for data base management system software was dismissed without prejudice by the General Services Board of Contract Appeals on August 9,1985. Dismissal of the protest was subject to certain conditions including furnishing of copies of NRC documentation regarding evaluation and award of the contract and holding a conference to discuss relevant information. After review of the documentation, Software AG declined the need for the conference.

2. On August 16, 1985, Compucom Security, Inc. filed a protest with the General Services Board of Contract Appeals (GSBCA) against a revised Request for Quotation (RFQ) 0001. The RFQ was issued as a brand name or equal for ADP Software, flultifunction Expansion Boards. Compucom Security, Inc. contends that the specifications are unjustifiably restrictive and are in excess of the minimum needs of the NRC. The award has been suspended pending the results of the hearing before the GSBCA.

ENCLOSURE A AUG 2 31985

OFFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending August 23, 1985 Davis-Besse On August 14, 1985, NRR issued a 50.54(f) letter to Toledo Edison Company due to the June 9, 1985 loss of all feedwater event at Davis-Besse. Pursuant to 10 CFR 50.54(f), the licensee is to furnish, under oath or affirmation, no later than 30 days from the date of the letter, their plans and programs to satisfy NRC concerns. The plan and programs are to specify those actions to be completed prior to restart of Davis-Besse and include a schedule for any longer term actions. There were three pages of expressed NRC concerns in the letter which fell into three broad categories as follows:

A. Completion of the investigation of the June 9, 1985 event, including analysis of the equipment failures, determination of the root causes, determination of the implications for other equipment, and completion or corrective actions.

B. The plant-specific findings regarding this event including the concerns identified in the NRC Fact Finding Team Report, NUREG-ll54.

C. The programmatic and management issues that have contributed to this event and more generally to the recent performance of Davis-Besse.

The NRC letter then requests the licensee to reexamine programs initiated under their Performance Enhancement Program (PEP) in light of the response to this letter.

This 50.54(f) letter also supersedes the Confirmatory Action Letter issued June 10, 1985 by Region III as lead responsibility for NRC staff actions relating to facility restart has been transferred to NRR. As per the June 10, 1985 Confirmatory Action Letter, it remains the staff's understanding that Davis-Besse will not be restarted without NRC approval.

Diablo Canyon Unit 2 Diablo Canyon Unit 2 is expected to achieve criticality between Sunday, August 18 to late Monday, August 19, 1985. The low power testing program would be completed about August 29. Based on the above schedule, Region V will notify Mr. Denton by letter, about four days after criticality as to readiness for full power license.

ENCLOSURE B AUG 2 31985

Dresden Unit 2 At 0021 CDT a site alert was called for Dresden Unit 2, when switchyard difficulties relating to Unit 1 resulted in a fault in the 138 KV switch-yard and tripped an auxiliary transformer causing a perturbation which then caused a unit trip and main transformer trip, hence loss of offsite power.

The diesel generators activated and picked up loads. A Group 1 isolation was manually initiated. Decay heat was removed with the isolation condenser and water level was stabilized by use of CRD pump 2A (2B unavailable - maintenance). Reactor pressure and water level were stabilized.

The fault was determined to be transformer #12. Switching allowed it to be isolated and power was returned to the main transformer. Onsite power was restored at approximately 0540 CDT. The alert was downgraded to an unusual event which was lifted at 0925 CDT.

A very slight amount of radiation was released onsite through the isolation condenser vent. This level of radioactivity is still being evaluated. The plant is currently at hot standby.

San Onofre Nuclear Generating Station, Unit No. 1 On Friday, August 9, 1985, the failure of a diaphragm caused a relief valve in the reactor coolant post-accident liquid sampling system to open.

The PASS cubicle was then flooded with clean water normally used to flush the PASS lines after sampling. A sump pump was set for manual operation and thus did not operate. The flooding was discovered by an operator. As a result of the submergence, all post-accident liquid sampling system at San Onofre Unit 1 capabilities are inoperable. The licensee expects to restore the capability to take undiluted grab samples in four weeks.

Shoreham On August 15, 1985, at 8:40 pm, the Shoreham Plant was raising reactor power to about 2.5% to perform HPCI testing when one of the turb.ine bypass valves started to oscillate, causing a spike in reactor power. The licensee attempted to control the oscillation by adjusting the reactor pressure regulator, but two more oscillations occurred. The last one caused a power spike to approximately 5.5% power. The licensee has suspended testing until it can investigate the cause of the oscillations and correct it.

ENCLOSURE B

AUG 2 3 5

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! Seabrook I

The joint owners of Seabrook Station, at a regularly scheduled meeting i held on August.14, 1985, voted to increase project funding to a level of $8 million per week effective September 1.

The increase from the $5 million per week funding level not in place is conditioned on the lifting of a Public Service Company of New Hampshire j (PSNH) spending restriction by the New Hampshire Public Utilities Commission (NHPUC). PSNH is currently limited to contributing no more

, than its share of a $5 million per week funding level. The owners also L voted that the $8 million per week funding level will be retroactive to j August 1, subject to the lifting of the spending restriction.

The increase in funding to $8 million per week is being made to keep the project on target for operation before the end of 1986.

Catawba Units 1 and 2

! On August 15, 1985, Unit 1 was operatinq at 94% power and Unit 2 was undergoing preoperational testing. While the Catawba Unit 1 operator was attempting to perform a routine operability test on the "B" diesel

generator (DG), he actuated the wrong breaker which caused a blackout

! signal. The DG actuated and performed as designed. The Unit 1 "B"

! motor-driven AFW pump and the turbine-driven AFW pump started

! automatically due to the blackout signal but were immediately secured.

j A temporary loss of containment cooling water, caused by the loss of l incoming bus, resulted in an increase in Unit 1 containment temperature and pressure. In addition, an outlet valve off the Unit 2 volume control

,. tank (VCT) (powered from a bus being supplied from Unit 1) closed resulting in the VCT having no outlet. At that time, the Unit 2 primary system was water solid with the positive displacement (PD) char aligned to take suction from the refueling water storage tank (ging)

RWST . pump

-This condition was unnoticed by the Unit 2 operator who was away from the controls responding to a request from the Unit 1 operators to assist them in the blackout recovery. Both Unit 1 temperature and pressure returned to normal following a containment air release sand restoration of contain-ment cooling water. The Unit 1 bus was subsequently realigned and the DG secured. But, on the Unit 2 side, the primary system letdown to the VCT l

continued resulting in the filling and possible overpressurization of the

VCT. The actual pressure attained is unknown. Relief path was available i

but it is not known if relief valve opened. Relief valve setting is being verified.

l Unit 1 power level remained at 94% throughout the event. Please note that the Unit 2 VCT discussed above is a recent replacement of the one which

, was blown apart due to an overpressurization event on April 20, 1985.

ENCLOSURE B l AUG 2 31985

Diablo Canyon Unit 2 The Pacific Gas & Electric Company informed the NRC staff that Diablo Canyon Unit 2 achieved criticality at 2:16 am PDT, on August 20, 1965.

Arkansas Nuclear One, Unit No. 1 At 4:16 pm, Sunday, August 11, 1985, AN0-1 tripped on an anticipatory trip of loss of feedwater. The plant was at approximately 98% power at the time. The "B" Main Feedwater (MFW) pump tripped off on a signal of thrust bearing wear. The "A" MFW pump then tripped because of the Reactor Protection System received a signal of low pressure from the MFW pump "A." The Emergency Feedwater (EFW) system actuated normally. The operators manually initiated High Pressure Injection for about 30 seconds (150 to 200 gallons) when pressurizer level went below 40 inches (this is normal procedure). The licensee is repairing the WW pump bearing, checking the pressure switch of the "B" MFW pump, and correcting a secondary leak in a flange connection of a hand hole of a steam generator.

The licensee should be able to start up later today.

Hatch Units 1 and 2 -

Georgia Power has informed us, by letter dated August 16, 1985 that its equipment qualification schedule for Hatch Primary Containment H,, and 0 2 Gas Analyzers may slip beyond the current November 30, 1985 deadline.

If Georgia Power requests a schedule extension beyond November 30, 1985, the extension will have to be approved by the Comission. It has encountered a delay in LOCA qualification testing, by COMSIP Inc., of the heat tracing on the tubing which feeds these Gas Analyzers. Georgia Power states that it expects that other BWR licensees whose equipment is being tested by COMSIP Inc. may be similarly affected.

Limerick Generating Station, Unit 1 On August 16,19M, an " Order Suspending Operation Above 5 Percent Power" was issued for Limerick Generating Station, Unit 1, on the basis of the stay by the United States Court of Appeals for the Third Circuit of the Commission's Order which authorized issuance.of Facility Operating License No. NPF-39. The court lifted its stay on August 21, 1985 and, accordingly, a " Rescission of Order" h u been issued by the Acting Director, Hugh L. Thompson, of NRR.

At 9:00 am on August 22, the plant was at 15 percent and proceeding to a plateau of 22 percent of full power. With sufficient water for six weeks operations, all the planned tests at this level can be completed.

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y,,j ENCLOSURE B s,e AUG 2 31985

Peach Bottom Atomic Power Station, Unit 3 Earlier this week, we were informed by both the Region and Philadelphia Electric Company that the current pipe inspections being performed as the result of Generic Letter 84-11 have uncovered at least 12 welds with crack indications. The majority of these welds had been previously examined in 1983 and found to be without cracks. They were then given induction heat stress improvement (IHSI) and again UT examined and found to be without indications. It has now been determined that at least one weld (10-02 20-inch RHR line) has a 360 degree circumferential crack approximately 35-55% thru-wall. The current Unit 3 inspections are relying primarily upon the new G.E. automated UT detection system called

"$ MART." It would appear that this new system has been able to detect cracks which has previously been missed in prior inspections. This issue of the quality of UT pipe crack inspections has also been raised by the staff after recent review of data resulting from the closer laboratory examinations of welds which had been obtain from various recirculation pipe replacement programs (i.e., evidence of missed crack indications).

A meeting with the BWR Owners' Group has been scheduled for the week of September 16, 1985 to discuss the issue of inspections as well as the status and direction of various industrial sponsored programs.

St. Lucie Plant, Unit No. 1 Florida Power and Light Company informed the staff on August 21, 1985 that Exxon Nuclear Corporation (ENC) had found an input error in its large break LOCA analysis for St. Lucie Plant, Unit No. 1. The error resulted in a calculated peak clad temperature that exceeds the limit of 2200*F established in 10 CFR 50.46. Initial results indicate that this limit could be exceeded by as much as 250*F at a linear heat rate of 15.0 kw/ft.

Earlier this year a code error was discovered by EXXON that led to a reanalysis for St. Lucie 1 that predicted a peak clad temperature of 2187'F for the large break LOCA.

In doing the original large break LOCA analysis for St. Lucie 1," ENC used assumed pump data as input to the codes, in particular, the torque curve. When the actual pump data and associated torque curve were applied, the peak clad temperature increased and exceeds the 2200'F limit.

The initial assessment indicates that a reduction in the linear heat generation rate setpoint from 15.0 kw/ft to 13.4 kw/ft will permit continued operation within the 2200'F limit of 10 CFR 50.46. The licensee has changed the setpoint to 13.4 kw/ft and, in addition, has voluntarily reduced power to 955 to provide a slightly greater margin of safety and provide some degree of flexibility.

The staff was advised that the other PWRs that might be affected have been reviewed and that actual pump data was used in each case and, l therefore, are not affected by the problem found at St. Lucie 1.

ENCLOSURE B AUG 2 31985

Cooper Nuclear Station Control rod withdrawal began at Cooper Nuclear Station during the afternoon of August 20, 1985, ending an ll-month refueling and maintenance outage. During the outage which began September 16, 1984, all reactor coolant piping susceptible to intergranular stress corrosion cracking (IGSCC) was replaced with IGSCC-resistant material, and the reactor was refueled for Cycle 10 operation. In addition to the refueling and pipe replacement, other major plant modifications were performed as part of the Appendix R, equipment qualification and NUREG-0737, Supplement 1 programs at Cooper Station.

After startup, the plant will undergo and extensive series of tests during power ascension. Return to full commercial power generation is expected to begin September 7, 1985.

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ENCLOSURE B c

AUG 2 3 M85

NRC TMI PROGRAM OFFICE WEEKLY STATUS REPORT WEEK ENDING AUGUST 23, 1985

1. PLANT STATUS

- The facility remains in long tern cold shutdown with the Reactor CoolantSystem(RCS)ventedtothereactorbuildingatmosphereand 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 erid is filled withwatertoadepthofabout20 feet (about5feetabovethetop of the plenum).

The modified internals indexing fixture is installed on the reactor ,

vessel flange and is flooded to elevation 327 feet 6 inches (151 feet above the top of the core region).

Calculated reactor decay heat is less than 12 kilowatts.

RCS cooling is by natural heat loss to the reactor building ambient atmosphere. Incore thermocouple readings range from 70*F to 92*F with an average of 80'F. Average cold leg temperature is 54*F.

The average reactor building temperature is 60*F. The reactor building airborne activity is 2.8 E-7 uCi/cc Tritium and 1.6 E-9 uCi/cc particulate, predominantly Cesium 137.

2. WASTE MANAGEMENT

- ' The Submerged Demineralizer System (SDS) and EPICOR II were shutdown this perioo.

Total volume processed through SDS to date is 2,963,375 gallons, and the total volume processed through EPIC 0F. II is 2,547,671 gallons.

Preparations are being cece to transfer the contents of condensate tank IA (C0T-1A) to EP]COR II. The tank will be oesludged and used as a storage tank for bor6ted makeup water.

4 AUG 2 31985 ENCLOSURE B

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3. DOSE REDUCTION /DECONTAf11 NATION 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. EllVIRONMENTAL MONITORING EPA sample analysis results show TMI site liquid effluents to be in accordance with regulatory limits, NRC requirements, and the City of Lancaster Agreement.

THI water samples taken by the US Environmental Protection Agency at the plant discharge to the river consisted of seven daily composite samples taken from August 3 to August 10, 1985. Gamma scans detected no reactor related radioactivity.

The Lancaster water sample taken at the water works intake and analyzed by the US Environmental Protection Agancy consists of a seven day composite sample taken from August 4 to August 10, 1985.

A gamma scan detected no reactor related radioactivity. ,

The NRC outdoor airborne particulate sampler at the TMI Site collected a sample between August 15 and August 22, 1985. No reactor related radioactivity was detected. Analysis showed I-131 and Cs-137 concentrations to be less than the lower limits of detectability.

5. REACTOR BUILDING ACTIVITIES Installation of the rotating work platform and service platform (over the reactor vessel) has been completed, llork on the north platform is in progress.

Installation of tool racks for defueling tools continues. The "D"

' tool rack is nearly complete; work is beginning on the "B" tool rack.

Defueling Water Cleanup System (DWCS) preoperational testing continued this week. The reactor vessel cleanup portion of the system is expected to be operational by mid-September.

6. AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES Installation of the DWCS continued. Partiel DWCS turnover for processing RCS during early defueling it capected to be completed in mid-September.

The second of four fuel canister racks ir er site with the remaining two scheduled for delivery in late August.

AUG 2 31985 ENCLOSURE B

3

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

Recovery Operations Plan Change numbers 29, 31, 32, and 34.

Fuel Canister Technical Evaluation.

Fuel Handling Senior Reactor Operator Training Program was completed August 22, 1985.

- Defueling Safety Evaluation. "

- Application for seismic exemption.

SDS Technical Evaluation and System Description Update

8. PROJECTED SCHEDULE OF FUTURE EVENTS

- Start of Defueling: October 1985

9. PUBLIC MEETING The next meeting of the Advisory Panel for the Decontamination of Three Mile Island Unit 2 is scheduled for September 11, 1985. The meeting will be at the Environmental Matters Committee Room (Room 160), House Office Building, College Avenue, Annapolis, Maryland from 6:00 to 9:00 PM. The purpose of the meeting is to inform the public of progress being made in the THI-2 cleanup and to allow the public to voice concerns and make comments on any aspects of the cleanup. The status of the processed water will also be discussed.

Persons desiring the opportunity to speak before the Panel are asked to contact 11r. Thomas Smithgall at 717-291-1042 or write to him at 2122 Marietta Avenue, Lancaster, Pennsylvania 17603.

t AUG 2 31965 ENCLOSURE B

s 0FFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending August 23, 1985 Near Term NRC Acticad Under the Nuclear Waste Policy Act (NWPA)

Section: 114(e) of NWPA Action: NRC received DOE Draft Project Decision Schedule on July 18, 1985.

Status: NRC comments are currently being sent to the Commission for concurrence.and transmittal to DOE by September 13, 1985.

Section: 301 of NWPA Action: DOE submitted its Final Mission Plan for the Civilian Radioactive Waste Management Program to Congress and NRC on July 9, 1985.

Status: NRC has been requested to testify on the Mission Plan before the Senate Committee on Energy and Natural Resources on Thursday, September 12, 1985. Proposed testimony is currently being sent to the Commission Section: 121(a) of NWPA Action: EPA signed its final high-level waste standards on August 15, 1985.

Status: The standards will be published in the Federal Register the week of August 26-30, 1985. NRC must revise 10 CFR Part 60 to conform to the EPA standards.

NFS-Erwin The strike by OCAW Union members continues. On August 14, 1985', letters from

, the Division of Safeguards and the Division of Fuel Cycle and Material Safety, MSS, were sent to NFS stating that the NRC had no objections to NFS conducting limited operations of the high enriched uranium production and scrap recovery facilities. NFS introduced material into the HEU production area on August 17, 1985.

ENCLOSURE C

. AUG 2.91985

- 2.-

General Electric Company, San Jose, CA License No. SNM-54 was terminated on August 20, 1985. The license, issued in 1967, authorized GE to possess enriched uranium for the production of fuel assemblies for light water reactors. After the start-up of the GE facility in Wilmington, N.C., production was gradually phased out and the major activities at San Jose centered around R&D. .The two main buildings where production took place were decontaminated and released for unrestricted use. R&D activities have decreased to the point where these could be assumed under the State license. Accordingly, the State of California amended GE's license to authorize GE to possess small quantities of special nuclear material.

Public Service Electric and Gas Company On August 21, 1985, Public Service Electric and Gas Company was issued Materials License No. SNM-1953 for Hope Creek Generating Station, authorizing the receipt, possession, inspection, and storage of uranium enriched in the U-235 isotope contained in fuel assemblies in their shipping containers and spent fuel pool.

O i

i ENCLOSURE C l

l AuG 2 31925

I 0FFICE OF INSPECTION AND ENFORCEMENT Items of Interest Week Ending August 23, 1985 Y

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

a. EN 85-56, a Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $5,000 was issued on August 20, 1985 to Astrotech,Inc.(Harrisburg,PA). This action is based on twelve violations which represent a lack of adequate management oversight and control of licensed activities.

b. EN 85-57, a Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $100,000 was issued on August 20, 1985 to Florida Power and Light Company (Turkey Point Units 3 & 4). This action is based on the failure of the licensee's staff to determine whether a modification to the spent fuel pits (SFP) piping created an unreviewed safety question. This failure resulted in the opera-tion of SFP systems for several years in a different manner than that described in the Final Safety Analysis Report.

c. EN 85-58, a Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $2,500 was issued August 22, 1985 to Hurley Medical Center (Flint, MI). This action is based on multiple viola-tions that represent a breakdown in management oversight and control of the licensee's health physics program. Among the violations involved are: (1) using licensed material in an unauthorized loca-tion; (2) improper disposal of licensed materials; and (3) failure to perform surveys.

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

> week:

(

a. PN0-I-85-59, Long Island Lighting Company (Shoreham), Unplanned Power Excursion.

b. PN0-II-85-79A, Nuclear Fuel Services, Incorporated (Erwin, TN), Update on Resumption of Limited Operations Under Strike Conditions.

c. PN0-II-85-80, Tennessee Valley Authority (Sequoyah Units 1 & 2),

Shutdown Greater Than 48 Hours.

d. PNO-II-85-81, South Carolina Electric & Gas Company (Summer),

Unscheduled Shutdown Greater Than 48 Hours.

e. PNO-II-85-82, Florida Power Corporation (Crystal River Unit 3), High

- Pressure Turbine Vibration,

f. PN0-II-85-83, Georgia Power Company (Hatch Units 1 & 2), Receipt of Punctured Waste Oil Drum in Washington State.

ENCLOSURE D ,,

AUG 2 31985

g. PN0-III-85-71, Comonwealth Edison (Dresden Unit 2), Loss of Offsite Power.

h. PN0-III-85-71A, Comonwealth Edison Company (Dresden Unit 2), Loss of Offsite Power (Update).

1. PNO-III-85-72, Comonwealth Edison Company (Byron Unit 2), Low-Level Contamination of Flushing System.

j. PN0-III-85-73, Comonwealth Edison Company (Byron Units 1 & 2),

Offsite Shipment of Contaminated Resins.

k. PN0-IV-85-39E, Western Stress (Evanston, WY), Apparent Overexposure of Two Radiographers (Final Update).

1. PN0-IV-85-42, Arkansas Power and Light Company (Arkansas Unit 1),

Outage Greater Than Two Days.

m. PN0-IV-85-43, Nebraska Public Power District (Cooper), Startup After ,

Extended Outage.

n. PNO-V-85-55, Pacific Gas and Electric (Diablo Canyon Unit 2), Initial Criticality.

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

a. IE Information Notice 85-71, Containment Integrated Leak Rate Tests was issued August 22, 1985 to all nuclear power reactor facilities holding an operating license or a construction permit.

b.. IE Information Notice 85-72, Uncontrolled Leakage of Reactor Coolant Outsite Containment was issued August 22, 1985 to all boiling water reactors holding an operating license or a construction permit.

4. Other Items ,

a. Senior Management Meeting Director, IE was in Region II August 22, 1985 to attend the Quarterly Regional meeting with Resident Inspectors.

b. Construction Appraisal Team (CAT) Inspection Chief, representatives, and consultants to, Reactor Construction Programs Branch, Division of Inspection Programs began CAT inspec-tions at Byron Unit 2 this week. The periods of inspection are scheduled as August 19-30 and September 9-20, 1985.

ENCLOSURE D AUG 2 31985

c. Small Scale Performance Appraisal Inspections Representatives of Reactor Operations Branch, Division of Inspection Programs started small scale performance appraisal inspections at D.C. Cook and Fort St. Vrain this week. Inspections will be conducted during the period August 19-23, 1985.

d. Irradiators Representative of Safeguards Materials Program Branch, Division of Inspection Programs was in Columbus, OH this week to observe the loading of CS 137 into the radiation sterilizer irradiator.

e. Containment Tendons Surveillance Representative of Engineering and Generic Comunications Branch, Division of Emergency Preparedness and Engineering response was at V.C. Summer facility August 21-22, 1985 to review previous contain-ment surveillance reports and to observe vertical tendon anchorages, and at the Vogtle facility on August 23, 1985 to review ongoing tendon installation, greasing procedures, and related information.

f. Transportation of Low-Level Waste Representative of Safeguards Materials Program Branch, Division of Inspection Programs presented a lecture on transportation of low-level waste at the DOE /0RNL sponsored " Workshop on Research and Development Needs for Treatment of Low-Level Radioactive Waste from Commercial Nuclear Reactor," on August 20, 1985 in Arlington, VA.

g. Vendor Inspections The Vendor Program Branch, Division of Quality Assurance, Vendor, and Technical Training Center Programs conducted the following inspections this week: ,

(1) Nine Mile Point Unit 1 (Syracruse, NY). To review licensee equipment qualification program implementation as required by 10 CFR 50.49.

(2) Bergen Paterson Pipe Support Corporation (Laconia, NH). To review the cause and corrective action taken on field identi-fied deficiencies in Bergen paterson hydraulic snubbers and to review current quality assurance and manufacturing activities applicable to in-process snubber work.

(3) FortCalhoun(Omaha,NE). To participate in an outage inspec-tion with Reactor Construction Programs Branch.

1 i ENCLOSURE D AUG 2 31985

h. Safeguards Training Representatives of Operating Reactors Program Branch, Division of Inspection Programs provided safeguards training at the Region II Resident Inspectors meeting on August 22, 1985,

i. Safeguards Meeting Representative of Operating Reactors Program Branch, Division of Inspection Programs met with the Midwest Nuclear Security Administra-tors Association this week in Fox Hill, WI to discuss safeguards issues.

j. Emergency Preparedness A representative of the Emergency Preparedness Branch, Division of Emergency Preparedness and Engineering Response is participating in an inspection of the University of Virginia research reactor this week.

k. Readiness Review Program On August 19-20, 1985, the Chief, Quality Assurance Branch, Division of Quality Assurance, Vendor, and Technical Training Programs parti-cipated in a meeting with Region II and NRR in Atlanta, GA to discuss lessons learned from NRC review of Module One of the Readiness Review Program so as to improve the review process for future modules.

t ENCLOSURE D AUG 2 31985 i

f 0FFICE OF NUCLEAR REGULATORY RESEARCH Items of Interest Week Ending August 23, 1985 Argonne National Laboratory A review of the program for modeling of two-phase flow at Argonne National Laboratory (ANL) was conducted on August 14, 1985. The purpose of the ANL program is to assess the scaling compromises in experimental facilities such as the Multi-Loop Integral System Test (MIST) and the University of Maryland (UM) 2 X 4 loop. As such, it is part of the Integral system Test (IST) program that will provide NRR data on the flow regime in the hot leg U-bend which is relevant to post small break loss-of-coolant accident (LOCA) transients for B&W reactors. The hot-leg U-bend experiment is an air-water experimental loop to study two-phase flow regimes, flow separation mechanisms and natural circulation termination for Babcock and Wilcox (B&W) type reactors. Procurement of parts to construct the scaled hot-leg U-bend (4 in. in diameter) facility using Freon is ongoing. Freon is used to simulate the boiling and condensation in the hot-leg U-bend as well as to check fluid property dependency'of flow regime transition. The other experiment being con-ducted is the inverted annular flow experiment using Freon to study the post-critical heat flux (CHF) flow regimes. The inlet to the test section has been modified to give two-phase (slug, churn and bubbly flow) inlet conditions. Data gathering and analysis is expected to be completed in March 1986. The model ahich is to be developed under this task has the potential of improving tae quench front modeling in NRC safety analysis codes such as TRAC and RELAP.

TRAC-BDI/ MODI Assessment TRAC-BDI/ MODI code assessment at the Idaho National Engineering Laboratory (INEL) is now completed. TRAC-BDI/ MOD 1 is a thermal hydraulics code having capabilities for calculating large and small break LOCAs and system transients in a boiling water reactor (BWR) and has been developed by RES for auditing vendor thermal hydraulic analyses in Chapter 15 submittals or evaluating operating procedures. The code has been assessed by comparing experimental data from various test facilities. The draft NUREG/CR report describing these results has just been received by NRC for comments.

l AUG 2 31985 ENCLOSURE E

Semiscale An unsuccessful attempt to run test S-FS-11, a 50 percent secondary feedwater line break was made on August 13, 1985. The test was terminated because of excessive leakage from the primary coolant system. It is postulated, although not known for certain, that a pressure sense line exiting from the top of the long tube in the steam generator was leaking.

A similar problem developed earlier in the FS series of tests and was corrected. If the sense line is the cause of leakage, it is estimated that the next attempt to run S-FS-11 will be about August 28, 1985.

Report EGG-SEMI-6985, " Pretest Analysis Document for Test S-FS-11" was also received this week.

Analysis of Potential Severe Core Damage Due to Safeguards-Related Inciderts Results of an analysis of potential severe core damage due to selected deliberate acts at nuclear power reactors were published in a Technical Letter Report, ORNL/NRC/LTR-85-6, July 1985. The purpose of this research project was to explore the feasibility of estimating relative contribution to public

• risk from known safeguards-related events with an existing analytical technique developed in the Accident Sequence Precursor (ASP) program at ORNL. The study reviewed 11 safeguards-related events that occurred during the period of 1980-1982. In none of these cases was it apparent that a deliberate attempt was made to cause core damage. Using this analytical technique, estimates of potential severe core damage were possible for 5 of the 11 safeguards-related events. The analysis estimated core damage probabilities of values greater 6 than 0.01 in two cases, if additional deliberate acts were assumed. However, the analysts concluded that the likelihood of such additional deliberate acts as a part of each event cannot be estimated because information concerning the intent of the person (s) causing each event is not known. Also, as part of the study, results related to safeguards events were compared to results of previous precursor analyses of safety-related incidents identified from Licensee Event Reports (LERs) in the same time frame.

ENCLOSURE E AUG 2 31985

Meeting with INEL on Alternatives to Shallow Land Burial Idaho National Engineering Laboratory (INEL) is under contract to NRC/RES to identify and evaluate the safety features and engineering design assumptions .

of engineered enhancements and alternatives to shallow land burial (SLB) for low level radioactive waste (LLW) disposal. On August 20, INEL researchers met with RES and NMSS staff to explain their research approach. INEL is applying risk assessment techniques, such as failure mode and effects analysis, to the various engineered components of several SLB altematives. To help them in their analyses they are using an adaptation of a LLW disposal technology classification scheme which keys on the particular engineered components that comprise various SLB alternatives. This scheme, developed ,

by Rogers and Associates Engineering, Inc. under contract to EPRI, facilitates '

the study of each engineered feature both as an individual component and as part of an overall engineered system. Moreover, this scheme avoids the potential complication which would arise from considering actual specific alternatives such as the Westinghouse "Sure-Pack" or the French tumulus.

Although the work is just beginning, it seems clear that INEL is progressing rapidly and soon will have a useful method for comparing the utility and expected perfomance of individual components of alternative LLW disposal methods.

Publications to be Issued in the Near Future 4

Title:

Criteria for Power, Instrumentation, and Control Portions of Safety Systems (Regulatory Guide)

Description:

This guide describes a method acceptable to the NRC staff for complying with the Comission's regulations with respect to the design, reliability, qualification, and testabi.lity of power, instrumentation, and control portions of safety-related systems.

Contact:

A. Hintze 443-7712

Title:

Criteria for Programable Digital Computer Systems Software in Safety-Related Systems of Nuclear Power Plants (Regulatory Guide) i

Description:

This guide describes a method acceptable to the NRC staff for complying with the Comission's regulations for promoting high functional I reliability for safety-related systems using programmable digital computers in the operation of nuclear power plants. The method is applicable to designing, verifying, and implementing software, and validating pmgrammable digital computer systems.

Contact:

A. Hintze 443-7712 l

l ENCLOSURE E MG23IE 1

L.____ _ _ __ _________. _ __,. _ _ _ _ _ ___ _ .- _ .

Title:

Design of An Independent Spent Fuel Storage Installation (Dry Type)

(Regulatory Guide)

Description:

Endorsement of ANSI /ANS 57.9.

Contact:

W. Pearson 443-7663

(

ENCLOSURE E

, AUG 2 3 MS

ITEMS OF INTEREST OFFICE Ce INTERNATIONAL PROGRAMS WEEK LNDING AUGUST 23, 1985 International Visitor On Monday Mr. S. Benassai of the Standards Division of Italy's National Committee for Research and Development of Nuclear Energy and Alternative Energy (ENEA) visited NRC for discussions with NRR and RES. Subject areas covered include permissible radiation dosage rates and frequency of in-service inspection of steam generator tubes.

Foreign Trip Report H. J. Faulkner, Chief, Technical Liaison Section, IP May 23-June 5, 1985; Visited Taiwan and Japan:

Mr. Faulkner attended the annual meeting of the Joint Standing Committee on Civil Nuclear Cooperation between Taiwan and the U.S. on May 28-29, 1985, in Taipei. Discussions were held with Atomic Energy Council, Taipower, and INER representatives on thermal-hydraulic code assessment, the severe accident program, cooperation in nuclear emergencies, reactor aging and IPIRG programs. On May 30 he visited the Maanshan plant. In Japan Mr. Faulkner met with officials of both MITI and STA to discuss the status of their activities regarding the renewal of our tripartite arrangement on regulatory safety matters and the planned visit to Japan by Chairman Palladino in August.

ENCLOSURE G AUG 2 31985 L

OFFICE OF STATE PROGRAMS ITEMS OF INTEREST WEEK ENDING AUGUST 23, 1985 Irradiator Workshop OSP is sponsoring a workshop on radiation safety in design and operation of large pool-type irradiators. State and NRC staff will attend. The workshop will be held 9/4-9/6 at Rutgers University and will include a field trip to a facility recently licensed by NRC.

Meeting with the State of Virginia On August 21, 1985, OSP and Region II staff members met with the Assistant Health Commissioner and staff in Richmond, Virginia. The State indicated its intention to proceed with full Agreement State status with NRC (excluding regulation of uranium milling) and also discussed its desire to enter into an MOU regarding inspection of low-level radioactive waste packaging and transportation at NRC licensed facilities.

ENCLOSURE H AUG 2 31985

OFFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA ITEMS OF INTEREST WEEK ENDING AUGUST 23, 1985 On August 21, 1985, AEOD met with the Region II resident inspectors and provided a status report on: AE0D organization and activities, new initiatives, and the proposed Incident Investigation Program. The results of an assessment of the 1984 LERs was also presented. A number of common problem areas and deficiencies noted in these LERs were identified and discussed.

On August 23, 1985, AE00 participated in discussions on the Davis-Besse event with the Region I resident inspectors. AEOD discussed the concept and principles of the proposed Incident Investigation Program and the process to be followed by NRC Teams. This presentation was followed by a discussion of the event by Ernie Rossi. NRC Team Leader, and comments on the investigation and event by Wayne Shafer, Region III Branch Chief.

O ENCLOSURE J AUG 2 31985

I 0FFICE OF SMALL AND DISADVANTAGED BUSINESS UTILIZATION / CIVIL RIGHTS Item of Iterest Week Ending August 23, 1985 t

Civil Rights program On August 15-18, 1985, the Office of Small and Ofsadvantaged Business Utiliza-fon and Civil Rights participated in " Blacks In Government" Seventh Annual The National Training Conference, held at the Washington Hilton Hotel.

conference focused on the achievement of merit, equality, and excellence in civil service.

career development Conference workshops covered such important areas as:

and management; computer technology and appifcations; management training and

• development; financial planning and investments; and performance and productivity improvenent.

9 ENCLOSURE K I

. AUG 2 31985 l

OEPUTY EXECUTIVE DIRECTOR FOR REGIONAL OPERATIONS AND GENERIC REQUIREMENTS (DEDROGR)

Week Ending August 23, 1985 CRGR Attached is a summary of the CRGR activities for the period July 1 through July 31, 1985. Background material on topics reviewed by the Committee and the minutes of CRGR meetings are sent to the Commission. Copies are provided to the Public Document Room after the NRC has considered (in a public forum) or decided the matter addressed by the documents. Questions concerning this monthly report should be referred to Walt Schwink (492-8639).

6 ENCLOSURE M AUG 2 3 N06

Page I cf 4 Data: August 23, 1985 ~

2>

SUMMARY

OF CRGR ACTIVITIES E5 (July 1 through July 31,1985)

. e.

c4 Meeting No.

g[MeetingDate on (Announcement CRGR CRGR Recommendation Date) Agenda Status to EDO EDO Action 79 Review, Proposed Revision 2 Pending Additional work needed by both Priority EDO action taken 7/24/85 of RG 1.99, " Radiation Damage RES and NRR to address new to ensure coordinated to Reactor Vessel" information. CRGR recommended effort by NRR and RES.

to the ED0 that this be given Matter brought to priority effort. Subsequent to Commission attention by

_ Sponsoring Office - RES the meeting, RES requested that SECY-85-262 (July 26,

_ Category 2 Item this guide be dropped from 1985 and subsequent memo

_ Issue #121 further CRGR consideration of August 22, 1985.

pending coordinated review by NRR and RES.

Briefing, Request to 0MB Complete CRGR strongly encourages staff No action necessary.

for Approval to Continue to to assure that only necessary Impose the Reporting & and reporting and recordkeeping Recordkeeping Requirements requirements are imposed by of 10 CFR 50 NRC.

-Sponsoring Office - NRR

-Category 2 Item

-Item #122 Briefing, Pressure Isolation Complete CRGR suggested staff consider- No action necessary.

Valve Test Requirements ation be given to the develop _

ment of better focused PIV

-Sponsoring Office - NRR guidance for the IST reviewers

-Category 2 Item and to assure plant-specific PIV

-Item #123 requirements for operating ES reactors were carried out con-fi sistent with NRC backfit procedures St (MC 0514).

gg __________________________________________________________________________________________________________

m 3

! Pag 2 2 of 4 Data: August 23, 1985 .

1

SUMMARY

OF CRGR ACTIVITIES (July 1 through July 31,1985)

c:

c>

• • Meeting No.

I* Meeting Date 8B CRGR CRGR Recommendation

'" (Announcement Agenda Status to EDO EDO Action Date) 79 (Continued) Review, Proposal for Complete CRGR recommended that this No action required at Improving Fire Protection issue be forwarded for con- this time because NRR sideration by the Commission has not yet taken a

-Sponsoring Office - NRR after resolution of the con- position on the CRGR

, -Category 2 Item cerns raised by the CRGR. recommendation.

t -Issue #117 i

! 78 Review, Proposed Requirements Pending CRGR reconnended issuance subject ELD review complete; Resulting frcm Resolution to review by ELD. package approved by EDO 7/8/85 for issuance for comment of USI A_46, " Seismic Qualification of Equipment and sent to Commission in Operating Plants" for information. No

' further action necessary

-Sponsoring Office - NRR at this time.

-Category 2 Item

-Issue #103 Briefing, Recommendations Pending Discussion at this briefing No action required at on Fire Protection Policy was inconclusive. CRGR this time.

and Program Actions will review this issue at Meeting #79 (7/24/85).

-Sponsoring Office - NRR

-Category 2 Item '

-Issue #117 m

5 E

A 2:

Dato: August 23, 1985 Page 3 cf 4

~

SUMMARY

OF CRGR ACTIVITIES 2

(July 1 through July 31,1985)

E5 to co Meeting No.

cs Meeting Date CRGR CRGR Recommendation 2R(Announcement Status to EDO ED0 Action Date) Agenda Complete CRGR offered several recom- No action required at 78 (Continued) Briefing, Proposed New SRP this time.

Sections to Address Expansion mendations relative to the SRP of Spent Fuel Storage section, but concluded that its issuance (for public comment),

as proposed by NRR, is appropriate.

-Sponsoring Office - NRR

_ Category 2 Item

-Issue #118 Briefing, NRC Activities Complete The CRGR noted that there No action required at in the Development of NDE appears to be an extensive this time.

menu of meaningful technical Qualification and Performance Demonstration Criteria development work ongoing.

Resources should be combined and focused on one path for early and adequate improvement

-Sponsoring Office - RES in regulatory requirements.

-Category 2 Item

-Issue #120 _________________________________

Subject to satisfactory staf

_________________________________________________________________________f Complete No action necessary at Review, Proposed Revision resolution of CRGR concerns, the this time because RES to 10 CFR Part 50 of has not yet taken a Appendix J (Primary Reactor CRGR recommends that the ED0 Containment Leakage Testing forward the proposed Appendix J position on the CRGR rule and accompanying RG MS 021-5 recommendation.

for Water _ Cooled Power to the Commission for approval.

Reactors)

E2 -Sponsoring Office - RES

[2 -Category 2 Item

-Issue #111 ll __________________________________________________________________________________________________________

x

- _. - - . - .. . -. . - - - . - - - -. . _ - . . - . . . - . . - - - ~ - . . - . - . - . _ _ - .-

Page 4 cf 4 Dat2: August 23, 1985 '

SUfMARY OF CRGR ACTIVITIES

> .(July 1 through July 31,1985)

C .

m to

ca Meeting No. ,

> g Meeting Date CRGR CRGR Recommendation m(Announcement EDO Action

! Date) Agenda Status to EDO i

1 Review, Proposed Amendments Complete CRGR recommends that the proposed No action required at j 78 (Continued) amendments be issued for public this time because IE 4 to 10 CFR 21, Reporting of i

Defects and Noncompliance and comment after modifications are has not yet taken a 10 CFR 50.55(e), Reporting of made. These modifications should position on the CRGR i

Defects in Design and be coordinated with the ROGR staff. recomendations, l

j Construction i

'I

! -Sponsoring Office - IE

{ -Category 2 Item 1 -Issue #119 1

i.

L

! l 1

1 l i

i

. P

m 3

ITEMS ADDRESSED BY THE COMMISSION - WEEK ENDING AUGUST 23, 1985 A. STAFF REQUIREMENTS - DISCUSSION /POSSIBLE V0TE ON FULL POWER OPERATING LICENSE FOR LIMERICK, 10:30 A.M., THURSDAY, AUGUST 8, 1985, COMMISSIONERS' CONFERENCE ROOM, D.C. 0FFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to E00 dated 8-21-85 The Commission

• met to discuss a full power operating license for Limerick Generating Station, Unit 1.

The Commission heard statements and comments from Phyllis Zitzer, President, Limerick Ecology Action; J.L. Everett, Chairman of the Board and Chief ERecutive Officer, Philadelphia Electric Company (PECo); and Vincent Boyer, Senior Vice President for Nuclear Power, PECo.

The Commission voted 4-0 to allow the Licensing Board's Fourth Partial Initial Decision to become effective and to authorize the staff to issue a full power license for Limerick Unit 1.

The Commission voted 3-1 (with Commissioner Asselstine dis-agreeing) to adopt an order (ref: SECY-85-267) implementing ,

the above vote. (This completes Commission action on SECY-85-267.)

(Subsequently, on August 8, 1985 the Secretary signed an order to that effect.)

The Commission further request'ed the staff to report to the Commission on the general performance of security personnel provided under contract to PECo and other licensees by YOH Security Inc.

(20181 (RI) (SECY Suspense: 9/13/85) i -

• Chairman Palladino was not present.

l ENCLOSURE O AUG 2 31985

.i l B. SECY 85-220 - ENVIRONMENTAL QUALIFICATION PROGRAM ACTIONS RESULTING FROM APRIL 2,1985 COPMISSION MEETING (Memo SECY to ED0 dated 8-27-85)

This is to advise you that the Commission (with all Commis-sioners approving) agreed that the attached Generic Letter, provided to you on August 2, 1985, be sent to all licensees of operating reactors.*

The Commission has also agreed to the following details for reviewing requests for extensions and for imposing civil penalties.

l. The staff shall review any requests for extensions of the November 30, 1985, deadline and provide an analysis and recommendation regarding action to the j Commission. Each staff submittal to the Commission should include a recommendation on whether the i extension should be granted. The staff

, recommendation should be sent to the Commission as soon as possible after receipt of the utilities request for extension. The Commission intends to advise licensees well in advance of November 30,

• 1985, of the Commission's decision on the extension request.

2. Utilities that are unable to comply with 10 CFR 50.49 by November 30, 1985, must have valid, staff approved JCOs to support continued operation. The staff is directed to require licensees to subm.it current JCOs for each item of non-qualified equipment for staff review and/or approval prior to the licensee being allowed to operate the plant in non-compliance. The Commission wishes to be kept

' - informed of those utilities which express a desire to operate in noncompliance and for each of the utilities in this category, the staff must inform the Commission that the utility has an approved JCo which is valid as of November 30, 1985..

l 3. The Commission approves the staff's proposal to use its enforcement discretion regarding enforcement actions against the limited number of plants which were not in compliance on or before their deadlines I (which were on or before March 31, 1985) and which have submitted untimely requests for extension. In l

determining whether enforcement is appropriate, the l

staff will consider whether adequate JCos were i'

provided and whether an extension would have been granted if timely filed. However, licensees in this situation are subject to the provisions of Generic Letter 85-15 after November 30, 1985.

Attachments (Not Included)

As Stated

{

AUG 2 31985

• Generic Letter 85-15 issued 8/6/85 ENCLOSURE 0

i EE, c

co ca 5$

sa NRR MEETING NOTICES *

• AUGUST 23, 1985 DOCKET i APPLICANT /

DATE/ TINE NUMBER LOCATION PURPOSE - ATTENDEES NRR CONTACT 8/26-29/85 50-498 Westinghouse To audit the veri ! cation Houston Lighting & N. Kadambi 50-499 Inst. Tech. and validation of the QDPS Power Co.

Trg. Ctr Bechtel Monroeville, PA . Westinghouse 8/26-30/85 50-245 Millstone Site To survey administration and 8:00 am Northeast Nuclear J. Shea Waterford, Conn. organization of the Maintenance Energy Co.

and Surveillance Programs 8/27/85 50-410 Nine Mile Point To review quality assurance Niagara Mohawk Power M. Haughey Site concerning the revetment Scriba, NY ditch 8/27/85 50-412 P-110 To discuss alternate pipe Duquesne Light Co.

1:30 pm Bethesda B. Singh rupture protection Stone & Webster 8/27-28/85 P-422 Working Meeting on specific EPRI 8:30 am D. Moran Bethesda generic safety issues impacting the EPRI/ Industry advanced LWR Requirements Document 8/28/85 50-387/ P-110 To discuss DCRDR schedule imple- Pennsylvania Power 10:30 am 388 M. J. Campagnone Bethesda mentation and unresolved Human and Light Engineering Deficiencies PLEASE BE ADVISED THAT DAILY RECORDING CAN BE HEARD ON 492-7166

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

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M2R MEETING NOTICES

• DOCKET , APPLICANT /

DATE/ TIME NUMBER LOCATION PURPOSE- ATTENDEES NRR CONTACT 8/28/85 50-354 Hope Creek Site Safety Parameter Display System Public Serv. Elec.

4:00 pm D. Wagner Lower A110 ways Design Verification and Vali- & Gas Co.

dation Audit .

8/28/85 50-286 P-114 To discuss exemptions to 1:00 pm Power Authority of J. Neighbors Bethesda Appendix R the State of NY 8/28/85 50-346 Davis Besse Site Discuss status of licensee's Toledo Edison 8:00 am A. De Agazio Dak Harbor, Ohio trouble shooting and correc tive actions, plant visit and discuss planned actions 8/29/85 50-528,529,530 2088-6110 To discuss scope of the small 9:00 as Arizona Public Serv. M. Ley Bethesda break LOCA analysis (Palo Verde)

I 9/4/85 50-346 P-422 Discuss licensee's planned l

9:00 am Toledo Edison Co. A. DeAgazio Bethesda actions relative to 6/9 event 9/4-5/85 50-289 P-114 Resolve open issues regarding GPU Nuclear Corp.

Bethesda Inservice Testing Program for pumps and valves, TMI-1 9/4-6/85 50-443/444 Seabrook Site Assess status of construction 9:00 am Public Service Co. V. Nerses Seabrook, NH . and completion schedule of New Hampshire PLEASE BE ADVISED THAT DAILY RECORDING CAN BE HEARD ON 492-7166

• 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.

m G

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MMSS MEETING NOTICES E . FOR WEEK ENDING: 08/23/85 .

Division cf Fuel Cyc17 and Materill Saf ty -

ra ATTENDEES / ' l Y. DOCKET -

NUPEER LOCATION PURPOSE APPLICANT NRC CONTACT

$ DATE/ TIE 8/26-30/85 Albuquerque,FM To attend workshop on subcritical G. H. Bidinger, FC Bidinger measurements. -

9/3/85 DOT, Washington, Pre-application meeting with DOT C. E. MacDonald, FC MacDonald .

D.C. for revalidation of Cas' tor MTR C. R. Chappell, FC Cask. R. R. Rawl, DOT GNS Representatives 9/3-6/85 New Brunswick, NJ Attend large irradiator radiation D. R. Chapell , FC Bassin ,

safety workshop for regulatory N. Bassin, FC personnel. J. Hickey, FC B. Carrico, FC 9/5/85 DOE, Washington, Meeting to discuss DOE /NRC/ DOT R. E. Cunningham, FC Cook ,

D.C. Regulatory / certification issues. C. E. MacDonald, FC

. J. Cook FC L. Barrett, et al, DOE

' Contractors 9/5-10/85 Idaho Falls. To discuss special site criteria W. A. Nixon, FC Nixon Idaho in EG1G developed reports.

. 9/6/85 (postponed fm. 5th. Floor Conf. Meeting to discuss nuclear stetho- R. E. Cunningham, FC Cunningham earlier date) Room SS scope training requirements. V. Miller, FC

. N. McElroy, FC W. J. Walker (Health physics Sys., Inc.)

9/6/85 Dak Ridge, TN Participate in Tennessee city / C. E. MacDonald, FC MacDonald county task force on monitored DOT - TN State and local ofcis.

retrievable storage.

9/9-12/85 Jackson, WY To attend and participate in 1985 N. Ketzlach, FC Ketzlach

,,, Nuclear Criticality Safety Topical G. H. Bidinger, FC .

M Meeting. K. Kodali, FC

, "o p -

IstSS IEETIIIG IISTICES PAGE 2 FOR EEK EIBIIIE: 8/23/85 E.

Division cf Fuel Cych and Material Saf;ty . .

u

• g 300EET ATTEIREES/.

M BRTE/ TIE IANGER LOCATISII PURPOW APPLICAllT INIC ColliACT -

9/10/85 lith Floor Conf. Meeting with United Kingdom R. Clark, UK Cunningham Room. W111ste officials regarding 10 CFR Part G. Webb, UK .

81dg., SS 20 exemption levels in de R. E. Cunningham, FC minimis, and high-level aiiid D. A. Cool, FC low-level waste. Representatives of WI, RES. and IIRR Division of Waste Management ,

None Division of. Safeguards None ,

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• • RES MEETI.*1G NOTICES August 23, 1985 c.

E DOCKET ,

PURPOSE ATTENDEES /

APPLICANT NRC CONTACT DATE/ TIE NtfBER LOCATION .

l '

Review status & draft report for GPC Au l 9/5/85 AR i 1:30 PM FIrl B8973 on task analysis of NRR l control room crews application: RES l

Part II Skills, Yaowledge &

Training 9/5-6/85 NL Review handbook on statistical PNL Frattali methods for nuclear material RES accounting Rfi 9/19/85 Auditorium, National Seminar on Liouefaction of Soil Beratan 9:00 AM- Acades;y of Sciences During Earthquakes 5:00 Pit Building Hazard at Saturated Soil Sites:

2101 Constitution Evaluation and Mitigation Ave., NW l

10/22-25/85 NBS 13th Water Reactor Safety Research Burda Gaithersburg, MD Information l'eeting (Preliminary Agenda attached)

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13th Water Reactor Safety Research Information Meeting This is a reminder that the Office of Nuclear Regulatory Research will hold its Thirteenth Water Reactor Safety Information Meeting at the National Bureau of Standards on October 22-25, 1985. The 4-day meeting will cover the results and plans of NRC's nuclear safety research programs.

Hundreds of representatives of government, industry, universities, public interest research groups and foreign nations have been invited to the 13th Water Reactor Safety Research Infonnation Meeting.

The 4-day session will focus on: Integral Systems Tests, Severe Accident Source Tenn, Seismic Research, Risk Analysis, Materials Engineering Research, Mechanical and Structural Research, Containment Systems Research, and the International Code Assessment Program.

Enclosed are copies of the preliminary agenda. ,Please give them wide distribution within your organization. Please note that NRC employees are not required to register unless they wish to have lunches provided and coffee breaks. The registration fee is $15.00 per day.

Further infonnation about the meeting and copies of the preliminary agenda can be obtained by calling Al Burda, Office of Nuclear Regulatory Research, 427-4468.

ENCLOSURE P g

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E E ~ EE -- .8 8 .6 . 8 I l ENCLOSURE P AUG 2 31985

                                                                                                                                                                                                         ],
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• to .

C.3 g T I . - ,,. t,. , Am.I .E.8 I.Rt.1 - .00m . easterials f astneerIns Reneere Code Assenessat and leprovement ladestry Safety Reneer e Pressure vessel Research metreem M. Veglas leflC) Solruma F. Oder f eelC) Solrmeer W. S. Leeusastela (18810 9 9:IS Crack Arrest Studlee Overvles, C. Pugh itpoILB 9:15 TRAC PFI/tect, D. Lites (LAseL3 9 IS Setety Inesearch la Transltlen. W. S. Leemmestels et al. 9:25 elde Piete Esperleents, R. Fleide fles) 9:35 TRAC-OesR, 2. Rouheal (EG&G) (EP4t t) 9:41 Oynamic Fracture Analyses, R. Seas (ORNL) 9:55 DELAPS, C. Johnson ([G4G) g s43 Steen Generster The lategrity, J. Leag and P. Relre 10:00 DevolePeent of Tisceplestic Fracture abchemics, 10:15 'ereek (EPute)

u. Kanalmen ($.sti) 10:30 COWtA/ TRAC, O. Trent (Ptoll 10:15 treek 10:20 treek 10:50 RANDent, P. Sehe f esti

• 10:30 Signet votidef fens A same ladestry Tool, S. Sua and 80:33 Fleel Res Its PT$t-Is Plants for PTSE-2, I t ale Overvlee of TRAC-Oust Assessments as. Olveheresol EtMell C. Pugh (ORIO TRAcel/te01-TRAC-eFB, C. Wilson EEGAG) 18:00 On-Clas Ostroelon Oroching smelter Devolesment, J. Gilmen 10 $S Reactor vessel Cledelag; Separate Effects Study, lleSO LAest TRAC-PFI/tt09 Code Assosoment Program using and R. Jones (ErstIt W. R. Corvia (ORNL3 LOFT and 0185 Osts. T. salght (LAest) 18:50 Severe Accident Centstament lategrity, % Tong et et.

01:20 Irredletten if f acts on Reactor vessels, Steels and 11:50 Assessment of TItaC-m>l/tt03 Umlag FIST Oste. (frgtl) testement tw$$f 4th & Sth $erles), R. K. smasted P. Sehe (DEL) 92:23 Poet APS Source fore Research, R. Tegel et al. (EPill) tORest) I2:IO RtLAPS/se02 Assesemmat at IsetL P. apneetiey (IssEL) I:00 Lesmch 51:45 Radletion Sensitivity and Anmeellag Parameter 12:30 Statue of TRAC PFI/ttX)I ladopendent Assessmeat et Studies, J. R. eenwthorse tee A) Sendle, L. Emptyk ($NL) 12:15 Lem-Oosleetry Program overvloe, W. 98 settf rey teWOLD ls00 Leach 12:40 Amector vessel Cevity 00slastry, J. Dutler (UntA(A) 1:00 Lunch PRIERT AFTUtStul - WWIN. IS,1999 etatorials feelmeerine Reneere 20/3) Reneerch theclear Plant Anatyrer Piplan Itosearch and Fracture sencheatco m etroen: M. senytteld tastC) Settmana 0. S. Shoe (estC) melruma C. R. Troutmen issuC) 2s00 let Ptfl testoriels and set Research, G. J. Llevd (UntA( A) 2 r00 Rosetts of CCTF Tests, Y. three (JAERil 2:00 lett Plant Analyser, f. T. Leets It0409 2:20 efic Plplag itseles Committee; Sommary en Pipe greehe, 2:35 Itoselts of ETF Tests, N Adecht (JA(RI) 2s)$ LAegL Plant Analyger, O. Llles ELAast) R. Klecher (9dIC) 3st$ Greek 3:15 Greek 2s39 Omgredad Peptag Progran . Phase il Progrees, 3:30 Anetytical Support for ETF, ETF and tA"FT Tests, 3:30 Del C--- , t et Dift Plant Analyser, W.1R:199, i C. Wilhowski E0(13 . J. Spore (LAesL)  % S. Geng, A. II. 90stlen and E. Csa amil (90 3:00 aresh 4:00 Status of Gernen (PTF Program, K. R. teofeena (Gt$) 4:00 Adjours m 3:15 Piping inneearch la the Federal Itapelle of Germoar, 4:30 Adjews N $chels (Gt$1 r 3:40 Piplag Itseeerch In Italy, P. Iellolle (EIEA) O a 05 Piplag Itosearch la Jopen, G. Vegese (U. Tokyo) W 4:30 Fractwo taperimeate en inlded Steintess steel Pipe, R. tesyee (0ftsUeCD 4:30 Piplag Frectare Beschemics Cote Gese, A. L. telger (stA)

     "O  Site Adjourn

m August 23, 1985 of gg es RII MEETING NOTICE gg m DOCKET ATTENDEES / PURPOSE APPLICANT NRC CONTACT DATE/ TIME HUMBER LOCATION 08/29/85 Soddy-Daisy, Presentation of Operator Licensee Operators, Grace 7:30 pm Tennessee License at Sequoyah TVA Management rep., Regional Adminstrator, selected Regional and Resident Staff Members E P 8

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