ML20211B379

Weekly Info Rept for Wk Ending 860530

ML20211B379
Person / Time
Issue date:	06/05/1986
From:	Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To:
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WIR-860530, NUDOCS 8606110618
Download: ML20211B379 (25)

Text

, b fDk June 5, 1986 For: The Commissioners From: T. A. Rehm, Assistant for Operations, Office of the ED0

Subject:

WEEKLY INFORMATION REPORT - WEEK ENDING MAY 30, 1986 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 Reports 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. '

/

/ m T. A. Rehm, Assistant for Operations Office of the Executive Director for Operations

Contact:

T. A. Rehm, EDO 492-7781 8606110618 860605 PDR COMMS NRCC WEEKLYINFOREPT PDR

. _ . - - _ . - I

HIGHLIGHTS OF HEEKLY INFORMATION REPORT WEEK ENDING MAY 30, 1986 Pilgrin Nuclear Power Station On May 27, 1986, during a press conference scheduled for 2:00 p.m., the Boston Edison Company announced its decision not to restart Pilgrim Station for another six weeks. The plant had been tentatively scheduled to restart this week following repairs of MSIVs and a LPCI injection valve and change out of the mode switch. However, the current strike by company entployees has apparently slowed these repairs. The 6-week extension of this outage allows two weeks for work on hardware and four more weeks to deal with programatic issues (primarily maintenance and radiation protection) raised in recent INP0 and SALP findings.

NINE MILE POINT 2

~

Mr. Charles Mangan, Senior Vice President for Niagara Mohawk Power Corporation, notified the staff by telephone that the Board of Directors have slipped the official fuel load date for Nine Mile Point 2 to l July 21, 1986. In a subsequent phone call from Mr. Anthony Zallnick, Licensing Manager for Nine Mile Point 2, it was also indicated that the schedule for criticality is August 18, 1986, and the schedule for commercial operation is March 28, 1987.

SCDAP/RELAP Application for the Chernobyl Accident INEL has received a contract from the UNC Nuclear Industries, which operates the N Reactor for the DOE, to perform a quick analysis on the initial phase of the Chernobyl accident. The SCDAP and RELAP5 codes will be used to analyze

' accident progression in a Zircaloy pressure tube - from the uncovery of 18 fuel rods inside the tube to fuel melt and failure of the tube wall. Because the SCDAP code has no provision for graphite properties and steam / graphite reactions, this analysis will not include steam / graphite reactions. Results will be made available to NRC for comments. The SCDAP/RELAP5 codes were developed and linked for use in NRC Severe Accident Research Program.

Perfonnance Indicators The interoffice performance group met March 20 and 21 to define a 1 trial program. The EDO was briefed on May 28, 1986 concerning progress and plans. At the next meeting on June 10 and 11 the group will discuss its plans with industry representatives (INPO and AIF).

mAY 3 0 W 1

OFFICE OF ADMINISTRATION Week Ending May 30, 1986 ADMINISTRATION OF THE FREEDOM 0F INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Carryovers, 1985 181 15 Received, 1986 396* 90 Granted 257 20 Denied 66 11 Pending 254 74

• During the week ending May 30, the NRC received 10 F0IA requests from Billie Garde for records regarding the Comanche Peak plant. She and other staff of GAP submitted a total of 27 F0IA requests in 1985 and a total of 30 requests to date in 1986 regarding the Comanche Peak plant.

ACTIONS THIS WEEK Received Harry H. Voigt, Requests three specified records regarding the TMI nuclear LeBoeuf, Lamb, power plant.

Leiby & MacRae (86-369)

Jennifer Puntenney, Requests three categories of records regarding the Safe Energy Fermi-2 nuclear power plant.

Coalition of America (86-370)

Patricia 8. Hough, Requests specified records and chronologies identified Science in the December 1,1977, memorandum from Edson Case to Applications Thomas McTiernan regarding the Diablo Canyon nuclear International Corp. power plant.

(86-371)

Billie P. Garde, Requests records related to Inspection Report 85-037, Government dated November 19, 1985, regarding SAFETEAM information Accountability concerning the Fermi nuclear power plant.

Project (86-372)

CONTACT: Donnie H. Grimsley 492-7211 ENCLOSURE A

2

. Received, Cont'd

' B11 lie P. Garde, Requests records regarding NRC evaluations, reviews, Government inspections, or conclusions done on the Fermi 2 Health Accountability Physics Department, January 1984 to the present.

Project (86-373)

Billie P. Carde, Requests records related to the Task Force on the Fermi 2 Government SAFETEAM allegations by NRR, IE, and Region III onsite Accountability June 27-28, 1985.

Project (86-374)

Billie P. Garde, Requests records related to Draft Office Letter #50, Government March 27,1986.

Accountability Project (86-375)

Billie P. Garde, Requests records related to Commissioner Bernthal's Government presentation to the Atomic Industrial Forum on May 20, Accountability 1985, in Dallas, Texas.

Project '

(86-376)

Billie P. Garde, Requests records related to the inspecti Government investigation of allegations by named individuals Accountability regarding the Nine Mile Point nuclear power plant.

Project (86-377) -

Billie P. Garde, Requests records related to 0I investigation 4-84-050, Government " Alleged Intimidation of TUGC0 Auditors by QC Accountability Management," noticsd in BN 86-14.

Project

-(86-378) ,

Billie P. Garde, Requests recorh % % r i to 0I investigation 4-84-039, Government " Alleged Intitud, av ., QC Inspector," noticed in Accountability BN 86-14, April 4, h_

Project (86-379) -

Billie P. Garde, Requests records related to Inspection Report 85-16/85-13 l Government regarding the Comanche Peak-nuclear pcwer plant.

l Accountability

Project (86-380)

Billie P. Garde, Requests records related'to Inspection Report 86-04/03 Government dated March 27, 1986, regarding the Comanche Peak nuclear Accountability power plant.

Project (86-381) ENCLOSURE A MAY 3 01986

3 Received, Cont'd Billie P. Garde, Requests records regarding Inspection Report 85-19, Government dated March 28, 1986, related to the Comanche Peak nuclear Accountability power plant.

Project (86-382)

Billie P. Garde, Requests records related to all NRC data on drug Government investigations at the Comanche Peak nuclear power plant.

Accountability Project (86-383)

Billie P. Garde, Requests records related to the June 29, 1984, meeting Government between TUEC officials and NRC staff regarding the Accountability investigations of illegal drug use at the Comanche Peak Project nuclear power plant.

(86-384)

Billie P. Garde, Requests records regarding a March 23, 1986, meeting Government between TUEC officials and the NRC at Region IV, including Accountability any memoranda prepared on consideration of whether the Project meeting was subject to 5 U.S.C. 552(b) " Sunshine Act" (86-385) provisions.

Billie P. Garde, Requests records related to EA-86-09 dated May 3, 1986, Government regarding the Comanche Peak nuclear power plant, including Accountabiltiy records which explain "other violations of NRC Project regulations were identified ...and were not included in (86-386) the package."

Billie P. Garde, Requests records related to Inspection Report 85-18/85-15 Government dated May 12, 1986, regarding the Comanche Peak nuclear

! Accountability power plant.

Project (86-387)

Robert W. Laza, Requests all annual reports prepared by Region III Theodore Barry & presenting comparative data for operation and construction Associates plants.

(86-388)

Ronald A. Rose, Requests copies of nine specified registration records F01 Services, Inc. for sealed sources and devices.

(86-389)

Ronald A. Rose, Requests copies of the latest radiological inspection F0I Services, Inc. reports for seven specified Ethicon (J8J) facilities.

(86-390)

MAY 3 01986 ENCLOSURE A

(

4 Received, Cont'd Patricia B. Hough, Requests two categories of records related to meetings Science between AEC/NRC staff and USGS staff between January 1,

Applications 1973, and December 31, 1985, regarding geology and International Corp. seismology during the review of the operating license (86-391) application for the Diablo Canyon nuclear power plant.

Michael P. Nunno, Requests a list of byproduct material licensees in the Elkins Park State of Pennsylvania.

Radiology Associates Ltd.

(86-392) ,

Brian Hunt, Requests four categories of records regarding Kerr-McGee's Environmental Sequoyah facility and the January 4,1986, incident at the Action facility.

(86-393) -

(An individual Requests five categories of records in Region II related requesting to his application for employment.

information about himself)

(86-394)

D. F. Bush, Requests all purchase orders originating from the Portland Parker Hannifin Valve and Fitting Company for the Trojan nuclear power Corporation plant during the period of December 1, 1985, to March 1, (86-395) 1986.

Marvin Resnikoff, Requests copies of the records denied in response to

. Sierra Club F0IA-86-152 regarding waste disposal at DOE's West Radioactive Waste Valley Demonstration Project.

Campaign (86-396)N l Granted Charles Barnes In response to a request for certain records from (86-117) (1) Docket 40-1668; (2) Docket 50-6589; (3) Docket 40-7271; and (4) Docket 40-6811, made available 167 records.

l i Billie P. Garde. In response to a request for records regarding Inspection i Government Report 50-445/84-39, made available four records. Informed Accountability the requester that one additional record subject to this Project request is already available at the PDR.

, (86-129) i (NRCemployee) In response to a request for records regarding an 0IA ,

(86-264) investigation, made availuble three records.

l Jim Pedro, In response to a request for o copy of Visual Weld NUS Corporation Acceptance Criteria for AWS Structural Welding at (86-341) Nuclear Power Plants, NCIG-01, submitted by NCIG on December 14, 1984, made available a copy of the requested rec h MAY 3 01986 ENCLOSURE A 4

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e.,.,,,-- ---- -

5 Granted, Cont'd Roberto Rivera, In response to a request for records regarding possible Roberto Rivera NRC contracts with CPA firms in Puerto Rico or the

& Co. U.S. Virgin Islands, informed the requester that the NRC (86-342) has no records subject to this request.

Jack H. Taylor, In response to a request for four categories of records Dallas Times related to the Soviet Union's nuclear industry and Herald marketed reactors, the April 1986 accident at the (86-343) Soviet Union's Chernobyl plant, and specified plants located in this country in the Office of Nuclear Regulatory Research (RES), informed the requester that RES has no records subject to this request.

Susan L. Hiatt, In response to a request for copies of records regarding OCRE Representative meetings held on April 18, 1586, and/or April 30, 1986, (86-348) between NRC staff, the Cleveland Illuminating Company, and the U.S. Geological Survey regarding the January 31, 1986, earthquake near the Perry nuclear power plant and related subjects, informed the requester that one record subject to this request is already available at the PDR.

Billie P. Garde, In response to a request for records regarding the Government March 23, 1986, meeting between TUEC officials and the NRC Accountability at Region IV offices, including any memoranda prepared on Project consideration of whether the meeting was subject to (86-385) 5 U.S.C. 552(b) " Sunshine Act" provisions, informed the requester that the NRC has no records subject to this request.

Denied Susan L. Hiatt, In response to a request for a copy of any testimony OCRE Representative prepared by NRC staff or consultants concerning the (86-324) January 31, 1986, earthquake in Ohio and its effects on the Perry nuclear power plant for presentation at the May 12, 1986, hearing on the Perry plant, denied three records in their entirety containing the opinions, views, and comments by NRC staff, the release of which would tend to inhibit the open and frank exchange of ideas essential to the deliberative process.

l l

l ENCLOSURE A 3 0 1906

~

WEEKLY INFORMATION REPORT DIVISION OF CONTRACTS WEEK ENDING MAY 30, 1986 PROPOSALS UNDER EVALUATION RFP No.: RS-0IE-86-155

Title:

" Technical Assistance for Design Inspections"

Description:

The design inspections are intended to provide a close examination of the design process and design implementation for a limited sample of structures, systems or components for a specific facility and any of its associated design organizations.

Period of Performance: 30 months Sponsor: Office of Inspection & Enforcement Status: The competitive range has been established and negotiations are scheduled for June 6, 1986.

RFP No.: RS-NRR-86-054

Title:

" Program to Support Regional Operator Licensing Activities"

Description:

Provide technical expertise to assist NRC regional offices in administering initial, replacement and requalification examinations required in the process of licensing comercial nuclear power plant reactor operators (RO) and senior reactor operators (SRO).

Period of Performance: Three years Sponsor: Office of Nuclear Reactor Regulation Status: Final Evaluation Report received on May 28, 1986.

CONTRACTS AWARDED

. RFP No.: RS-NRR-86-053

Title:

" Review of RETRAN Computer Code and Confirmatory Licensing Calculations"

Description:

Assist in review of RETRAN Computer Code for use in the analysis of non-LOCA transients and accidents.

Period of Performance: 11 months Sponsor: Office of Nuclear Reactor Regulation Status: A Cost-Plus-Fixed-Fee type Contract No. NRC-03-86-053 was awarded to SBA/

International Technical Services, Inc., in the amount of $242,909 effective May 9, 1986. This firm has been certified by the Small Business Administration as a socially and economically disadvantaged firm eligible for noncompetitive awards under that agency's 8(a) program.

RFP No.: RS-RG2-86-358

Title:

" Data Entry Support Services for NRC Region II Office"

Description:

Perform ADP Data Entry and ad hoc retrieval activities at NRC Region II.

Period of Performance: May 30, 1986 through May 29, 1988.

Sponsor: Division of Resource Management and Administration, Region II Status: A Cost-Plus-Fixed-Fee type Contract No. NRC-29-86-358 was awarded to MTSS, Inc., in the amount of $158,110.62 effective May 30, 1986.

ENCLOSURE A MAY 3 019tl6

~

0FFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending May 23, 1986 Point Beach Unit 1 Point Beach Nuclear Plant Unit 1 completed it's 13th annual refueling outage on May 21, 1986. The unit is currently at 90% power. Major activities completed during this refueling outage were replacing all condenser tubes, replacing the feedwater heaters, completion of environmental qualification of pressurirer safety valve position indication and installation of a new plant computer.

TMI-1 Commission Decision GPUN's December 5, 1979 NOV response to the TMI-2 accident raised serious questions concerning management integrity. It was prepared by Edward Wallace and signed by Robert Arnold. The Commission decided not to reopen the TMI-1 restart proceeding record on the issue of Arnold's and Wallace's involvement in the NOV because the significance of the issue, if any, was mooted by licensee's removal of Arnold and Wallace from TMI-1 operations.

The Commission required GPUN to notify it before returning either of these individuals to responsible positions at TMI-1 (CLI-85-2).

Both Arnold and Wallace requested NRC hearings to clear their reputations.

The Commission noticed these requests for public comment and seven sets of

- comments were submitted. By Order (CLI-86-09) dated May 16, 1986, the Commission made the following decisions:

(1) The Commission finds that there is no reasonable basis to conclude that Arnold made a knowing, willful, or reckless material false statement in the NOV response, and it does not view Arnold's involvement in the NOV as requiring any constraint on his employment in t*,e regulated nuclear industry. However, it will leave the notification requirement in effect for TMI-I because Arnold did not request its removal.

(2) The evidence regarding Wallace's involvement in possible willful, knowing, or reckless material false statements is much more difficult to evaluate and the request for a hearing is granted. All persons who filed previous responses to the Commission's request for public comments may petition to intervene. The staff will be a party. All others must satisfy the late filing conditions. Petition to intervene must be filed in 45 days. If no person intervenes against Wallace, and NRC staff does not advocate a position against Wallace, then the proceeding shall be terminated and the TMI-1 notification requirement as to Wallace shall be removed.

ENCLOSURE B MAY 3 01ll86 l

Pilgrim Nuclear Power Station On May 27, 1986, during a press conference scheduled for 2:00 p.m., the Boston Edison Company announced its decision not to restart Pilgrim Station for another rix weeks. The plant had been tentatively scheduled to restart this week following repairs of MSIVs and a LPCI injection valve and change out of the mode switch. However, the current strike by company employees has apparently slowed these repairs. The 6-week extension of this outage allows two weeks for work on hardware and four more weeks to deal with programmatic issues (primarily maintenance and radiation protection) raised in recent INP0 and SALP findings.

NINE MILE POINT 2 Mr. Charles Mangan, Senior Vice President for Niagara Mohawk Power Corporation, notified the staff by telephone that the Board of Directors have slipped the official fuel load date for Nine Mile Point 2 to July 21, 1986. In a subsequent phone call from Mr. Anthony Zallnick, Licensing Manager for Nine Mile Point 2, it was also indicated that the schedule for criticality is August 18, 1986, and the schedule for commercial operation is March 28, 1987.

I ENCLOSURE B MAY 3 0 566

i NRC TMI-2 CLEANUP PROJECT DIRECTORATE WEEKLY STATUS WEEK ENDING MAY 30, 1986

1. DEFUELING

- Pick and place defueling activities continued. The number of canisters transferred to the fuel pool remains at 42.

- On Sunday, June 1, 1986, video tape of the core was taken.

- The sixth and final batch in the current campaign of Reactor Coolant System (RCS) drain and refill was completed on Saturday, May 31, 1986.

- The Defueling Water Cleanup System (DWCS) was restarted on Saturday, May 31, 1986 and ran until Sunday evening June 1, 1986.

2. PLANT STATUS

- The reactor remains in long term cold shutdown, vented to the atmosphere. Core cooling is by natural heat loss to ambient building atmosphere. The average incore thermocouple reading is 84 F; reactor vessel water temperature as measured by resistance temperature detectors (RTD's) is 78'F. Water visibility is approximately 4 - 5 feet.

2. PLANT STATUS

- The airborne radioactivity on the defueling platform is about 3 E-7 uCf/cc Tritium and 8 E-11 uCi/cc particulates, predominately Cesium-137 and Strontium-90. The platform is mounted above the modified internals indexing fixture which is mounted over the reactor vessel. These provide about 15 feet of water over the core region and 6 feet over the carousel holding the defueling canisters.

3. WASTE MANAGEMENT

- The Submerged Demineralizer System (SDS) and EPICOR II remain in temporary shutdown. The SDS has processed 3,954,097 gallons through batch S-131. EPICOR II has processed 2,925,820 gallons through

batch 287. The next processing will be the RCS drain-down water from B and C Bleed Tanks, about 75,000 gallons.

l - To assure a maximum kill-off of the microbial growths throughout the water storage and processing systems, the licensee plans a tank-by-tank application of hydrogen peroxide. This will include the processed water storage tanks, the EPICOR II discharge and feed tanks, the neutralizer tanks, and the miscellaneous waste holdup tank.

MAY 3 01966 i ENCLOSURE B

2

4. ENVIRONMENTAL MONITORING US Environmental Protection Agency (EPA) sample analysis results show that TMI site liquid effluents are in accordance with regulatory limits, NRC requirements, and The City of Lancaster Agreement.

- The Lancaster water sample taken at the water works river intake and analyzed by EPA consisted of a seven day composite sample taken from May 10 - 17, 1986. A gamma scan detected no reactor related activity.

TMI water samples taken by EPA at the plant discharge (includes Units 1 and 2) to the river consisted of seven daily composite samples taken from May 10 - 17, 1986. A gamma scan detected a trace amount of Iodine-131 in the May 15 - 16, 1986 sample.

The EPA analysis of the NRC outdoor sampler for the period May 22 -

29, 1986 showed that concentrations of Cs-137 and I-131 were below the lower limit of quantitative detectability for the system, i.e.,

less than 1.1 E-13 microcuries/cc. A trace of I-131 was detected in the sample. The unquantifiably small traces of I-131 are probably from the Chernobyl accident.

5. AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES Water flushing was performed in the Westinghouse Valve Room (281' Auxiliary Building) over the past week. This room abuts the annulus and is the location of the mini-decay heat cooling system. This is the first major decontamination of the room.

Assembly of the Desludging system continued.

On May 30, 1986, one of the rail shipping casks was moved into the fuel handling truck bay to assist in lining up the cask unloading station framing. The testing program continues on the transfer shield.

6. NRC EVALUATIONS IN PROGRESS

- Technical Specification Change Request number 49, and 51.

Recovery Operations Plan Change number 31, 33, 35, and 36.

- Solid Waste Facility Technical Evaluation Report.

Reactor Building Sump Criticality Safety Evaluation Report.

Canister Handling and Preparation for Shipment Safety Evaluation Report.

- Defueling Canister Technical Evaluation Report, Revision 2.

- On May 28, 1986 the NRC approved GPUN's safety evaluation report for Core Stratification Sample Acquisition, Revision 3.

7. PUBLIC MEETING l The Advisory Panel for the Decontamination of TMI-2 will meet with the NRC Comissioners on June 11,1986 at 11:00 AM. The meeting will be held l at the NRC conference room at 1717 H Street, N.W., Washington, DC.

MAY 3 01986 ENCLOSURE B l

OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending May 30, 1986 Near-Term NRC Actions Under the Nuclear Waste Policy Act of 1982 Section: 121(a) of NWPA: EPA Final HLW Standards Status: The proposed Federal Register notice of revisions to conform Part 60 to EPA Standards (SECY-86-92) was submitted to the Commission on March 26, 1986, and was approved without modifica-tion for publication in the Federal Register.

Action: Staff is currently preparing the notification for publication in early June.

Section: 114(e)(2) of NWPA: Federal Agency Reporting Requirements Status: With the issuance of the final Project Decision Schedule (PDS) on April 3, 1986, the reporting requirements of Section 114(e)(2) are now effective. Any Federal agency that determines that it cannot comply with any deadline in the PDS, or fails to comply, is required to report to the Secretary of Energy and to Congress, explaining the reason for such actual or potential noncompliance.

Action: Staff is currently reviewing the final PDS for near-term deadlines for NRC action that all under Section 114(e)(2) of NWPA.

Section: 306 of NWPA: Regulations for Training of Power Plant Personnel Status: The final rulemaking (SECY-86-123) on Part 55 and three associa-ted regulatory guides concerning regulations for Training of Power Plant Personnel are currently under review by OGC for sub-sequent Commission approval.

Near-Term Actions Under the LLRWPAA Section: 10 of LLRWPAA: Exemption of specific waste streams from regulation.

Provision: By July 1986, NRC must establish standards, procedures, and tech-nical capability to act upon petitions to exempt specific waste streams from NRC regulation.

Action: Staff will forward its recommended policy to the Commission in June 1986.

MAY 3 0 E86 EllCLOSURE C

. l Office of Inspection and Enforcement Items of Interest Week Ending May 30, 1986

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

A Notice of Violation and Proposed Imposition of Civil Penalty was issued to Georgia Power Company (Hatch) in the amount of $50,000. This action was based on multiple security violations involving compliance failures and inadequate compensating actions at the protected and vital area barriers (EN 86-33).

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

a. PNO-I-86-39, Pennsylvania Power & Light Company (Susquehanna) -

Failed ESW Pump.

b. PNG-III-86-49A, Consumers Power Company (Palisades) - Augmented Investigation Team to Review Recent Equipment Problems (Update).

c. PNO-III-86-50, American Electric Power (D.C. Cook), Unplanned Trip; Sell Leak in Primary System.

d. PNO-IV-86-18, Sequoyah Fuels Corporation (Gore, OK) - Attack on Security Guard.

e. PNS-V-86-04, Arizona Nuclear Power Project (Palo Verde), Bomb Threat.

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

IE Compliance Bulletin No. 86-01, Minimum Flow Logic Problems that Could Disable RHR Pumps was issued to all GE Boiling Water Reactor facilities holding an operating license or a construction permit.

4. Other Items

a. Civil Penalties Paid Portland General Electric Co. (Trojan) in the amount of $80,000, based on failure to maintain control room emergency ventilation in j operable status (EA 86-54).

b. Operations Center l Incident Tracking Team, are winding down their coordination of NRC's i

support to EPA through the Operations Center. Radiological

measurements continue to be received, entered, and plotted by l fractions of EPA Protection Action Guidlines (PAGs) by day.

MM30 g ENCLOSURE D l

l q ._ _ _ _ . _ _ , _ _ , , _ _

c. Incident Response A member of the Incident Response Branch attended the monthly meeting of the National Response Team (NRT) this week,

d. Vendor Program The following Vendor Program Branch inspection is being conducted this week:

Golden Gate Forge and Flange Co., San Francisco, CA - tc obtain information regarding potentially fraudulent activites associated with material supplied to nuclear power plants.

e. Emergency Preparedness

1. A member of the Emergency Preparedness Branch participated with NRR and Region IV in a site visit at South Texas to discuss emergency plans.

2. An emergency preparedness exercise report provided by FEMA for Kewaunee was forwarded by IE to Region III for transmittal to the licensee. No deficiencies were observed in offsite preparedness during the exercise.

f. Performance Indicators The interoffice performance group met March 20 and 21 to define a trial program. The EDO was briefed on May 28, 1986 concerning progress and plans. At the next meeting on June 10 and 11 the group will discuss its plans with industry representatives (INP0 and AIF).

g. ACRS Briefings On June 3, 1986, members of IE and NRR staff will brief the ACRS Subcommittee on Reactor Operations and on June 6, 1986 regarding recent significant operating events at nuclear power plants.

h. Meetings - Conferences of Note (1) Members of the DQAVT are attending a meeting of the Coordinating Committee for NRC/ASME/ National Board in New York City.

(2) Division Director, DEPER and Emergency Preparedness Branch Chief will be attending the EPRI Information Meeting on "The EPZ and the Source Term" in Upton, Long Island on June 1 - 3, 1986.

(Jordan)

ENCLOSURE D MAY 3 01986

OFFICE OF NUCLEAR REGULATORY RESEARCH Items of Interest Week Ending May 30, 1986 Multi-Loop Integral System Test (MIST) Program i The MIST facility is an integral test facility designed to simulate thermal hydraulic aspects of transients in reactors of the Babcock and Wilcox (B&W) design. The experimental data will primarily be used to compare against small break loss-of-coolant models as required by TMI-2 Task Action Plan Item II.K.30. The 12th Program Management Group (PMG) Meeting for this program was held on May 12-13, 1986 in Washington, D. C. The PMG reviewed the status of the MIST program. Results from some of the characterization testing such as calibration of thermocouples, measuring loop volumes and irrecoverable pressure drop, etc., were presented at the meeting. Composite testing will commence in June and is scheduled to finish at the end of 1986. Toledo Edison Company (Davis-Besse reactor) requested four tests concurrent with the current program.

Three of the four tests will provide experimental data to support installation of a continuous vent line between the reactor vessel head and the upper plenum of a steam generator. The remaining test is to provide experimental data on Feed and Bleed capabilities to compare with an existing code prediction of plant transient behavior. The cost of these tests will be paid by Toledo Edison. The PMG approved Toledo Edison's request to add four tests to the program.

During the meeting, the status of research projects in support of the MIST program such as the University of Maryland B&W 2x4 Loop sponsored by the NRC and various research projects sponsored by the Electric Power Research Institute were presented. In addition, four out of the five pre-test predictions using the Transient Reactor Analysis Code (TRAC) completed by Los Alamos National Laboratory were shown. An elaborate control system was implemented in TRAC for the calculation. The incorporation of the control system has improved the efficiency of the calculations because it automated all the trips during the simulation of the transients. Three of the pre-test predictions were intended to examine whether the simulated core and the code safety relief valves of MIST will be challenged during testing. The results showed that the simulated core will not be uncovered during the course of the transient, and the facility high pressure limit will not be reached and, hence, the code safety valves will not lift. The next PMG meeting is tentatively scheduled for August in Alliance, Ohio.

ENCLOSURE E

. 2 SCDAP/RELAP Application for the Chernobyl Accident INEL has received a contract from the UNC Nuclear Industries, which operates the N Reactor for the DOE, to perform a quick analysis on the initial phase of the Chernobyl accident. The SCDAP and RELAPS codes will be used to analyze accident progression in a Zircaloy pressure tube - from the uncovery of 18 fuel rods inside the tube to fuel melt and failure of the tube wall. Because the SCDAP code has no provision for graphite properties and steam / graphite reactions, this analysis will not include steam / graphite reactions. Results will be made available to NRC for comments. The SCDAP/RELAP5 codes were developed and linked for use in NRC Severe Accident Research Program.

" Reassessment of the Technical Bases for Estimating Source Terms (NUREG-0956)"

A high priority goal of NRC is to publish the final version of the

" Reassessment of the Technical Bases for Estimating Source Terms (NUREG-0956)"

by July 15, 1986. It is important to confirm that NUREG-0956 correctly portrays the contribution of each of the organizations participating in the source term work, that the laboratories stand behind their own work as incorporated in the NUREG, and that the laboratories have not identified any significant technical flaws in the document. On May 27-30, 1986, NRC/RES staff visited BNL, INEL, ORNL, and SNL to facilitate final review of the document to support our publication goal and to assure that the desired high technical quality is achieved.

The objectives of NUREG-0956 do not include the determination of plant-specific source tenns or the determination of the probabilities of accident initiation or of containment failure. Instead the document describes a significantly I improved capability to calculate source terms, provided the accident sequence has been otherwise defined. NUREG-1150 will provide the NRC staff definition

( of specific source terms and other probabilities for six reference plants.

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ENCLOSURE E l MAY 3 01986

3 RES RULEMAKING ACTIVITIES AND OTHER RELATED ISSUES Risk Effectiveness of LWR Regulatory Requirements In 1985 Policy and Planning Guidance on improving regulation of the nuclear industry the Comission directed the staff to review existing regulatory requirements to see if some could be eliminated without compromising safety.

In response to this guidance, RES is continuing a 1985 program to select existing rules for reexamination based on a comprehensive evaluation of their risk significance. Rules that have marginal importance to safety or that have become obsolete by implementation of other approved staff practices will be recomended for elimination or modification.

The contractor's Task 1 report, sumarizing those regulatory requirements that appear to have marginal importance to safety, was published as NUREG/CR-4330, Vol.1, a' the end of April 1986. The camera-ready copy of the Task 2 report was received on May 19, 1986. The Task 2 report presents the results of detailed risk and cost analyses of three selected regulatory areas: (1) allow-able leakage rates for reactor containment, (2) leakage control system for main steam isolation valves, and (3) regulatory review of fuel design. The draft staff recomendations concerning containment leakage is being revised to incorporate comments from members of advisory groups and consultants. A final version of staff recommendations is expected to be ready for office concurrence in June 1986.

The draft Comission information paper to report the progress of the Risk Effectiveness Program and a draft Federal Register notice to announce the availability of the two contractor's reports are being revised to incorporate comments received from the office representatives in the Program Advisory Group.

Shipping Cask Response to Severe Transportation Accidents--Modal Study The purpose of this study is to detennine the performance of licensed casks under various types of realistic accidents that might occur during shipments of spent fuel. This purpose is being accomplished by assessing the performance when subjected to severe transportation accident environments, as well as by assessing the likely frequency of such environments. A draft final report was received in April 1986.

ENCLOSURE E MAY 3 01996

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The NMSS-requested briefing on the objectives, approach, and results of the subject program was held at Lawrence Livermore National Laboratory on May 22, 1986. Four DOT and three DOE representatives attended the meeting. Two peer reviewers from the Denver Research Institute were also present. The presenta-tions were well received. An NMSS representative indicated that it was NRC's intent to issue the engineering report following the peer review. He also indicated that NRC tentatively intends to develop a sunnary document, based on the engineering report, which would be suitable for public distribution.

PRM-50-40--Requires Mandatory Reactor Shutdown if Cause of Reactor Trip Undetermined in 8-Hour Period In a petition for rulemaking filed on November 26, 1985, J. F. Doherty requested the subject action. The petitioner's concern stemmed from the 1983 Salem anticipated transient without scram event. Numerous comments on the proposed rulemaking (PRM) were received on the last day or following closure of the comment period. Most of the comment letters were sent by individual utility companies or their representatives. These utility coments emphasized the applicability of actions taken in response to Generic Letter 83-28 in lieu of the petitioner's reconnendation. Safety and economic reasons were presented arguing against the petitioner's recommendation that the reactor be placed in cold shutdown condition if the cause of a trip is not identified in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Responses to public comments are included u. the Federal Register notice. The

" denial of petition" package was sent out for office connent and concurrence on May 13, 1986. All offices concurred during the week of May 19, 1986.

MAY 3 01986 ENCLOSURE E

0FFICE OF STATE PROGRAMS ITEMS OF INTEREST WEEK ENDING !%Y 30, 1986 State Program Review The Tennessee radiation control program will be reviewed by Region II the weeks of June 9 and June 16.

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MAY 3 01996 ENCLOSURE H

OFFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA Week Ending May 30, 1986

1. An AE0D Engineering Evaluation report (AE0D/E606) on " Loss of Safety Injection Capability at Indian Point Unit 2" was issued on May 27, 1986.

On December 28, 1984, while the Indian Point Unit 2 reactor was critical, all three safety injection (SI) pumps were declared inoperable. Two pumps were inoperable due to low suction flow and the third pump could not be manually started. The reactor was manually scramed. While it was subcritical and a cooldown was in progress, a spurious SI signal occurred.

Since all SI pumps were inoperable and had been de-energized, no SI occurred.

The malfunction of the SI pumps was caused by boric acid crystallization and possible gas binding of the pumps. Two parallel leaky valves in the discharge line of the boron injection tank (BIT) enabled highly concen-trated boric acid to flow through the low pressure discharge line and to precipitate in the pumps which were not heat traced. Degassing of the nitrogen cover gas which had been dissolved in the boric acid solution is believed to be one of the likely sources of the gas found in the pumps.

The contribution of nitrogen from the isolation valve seal water system could not be verified.

The degradation of the SI pump performance due to boric acid crystalliza-tion is not a generic problem with Westinghouse (W) PWRs but is site-specific. Most W PWRs have their BIT downstream of the SI pumps.

However, besides Indian Point Unit 2, a few other W plants were designed with their BIT (or equivalent) located upstream of the SI pumps. Some additional plants that have the same configuration as Indian Point Unit 2 and use highly concentrated boric acid from their boric acid tanks have been identified.

The Indian Point Unit 2 event was reported to the Congress as an Abnormal l Occurrence. Also, NRR has sent a generic letter to all the licensees of W PWRs encouraging them to reassess their design basis steam line breaks to re-evaluate the need for highly concentrated boric acid. It is suggested that IE issue an information notice to make the licensees of the poten-tially affected }( PWRs more aware of this safety concern and to emphasize the need to follow strict administrative controls to prevent similar occurrences until their BIT is remove.

ENCLOSURE J MAY 3 01986

CD g NRR MEETING NOTICES

• 3 MAY 30, 1986 i

DOCKET APPLICANT /

DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT i

6/2/86 50-321 Region II Head- Meeting with Georgia Power Co. NRC/ Licensee G. Rivenbark 10:00 a.m 50-366 quarters Offices (GPC) representatives to dis-Atlanta, GA cuss the GPC plans related to Hatch Unit I and 2 and the .

status of Hatch I and 2 licen-sing activities l 6/3-4/86 50-213 Haddam Neck Plant Discuss plant operating ex- NRC/0RNL/NU F. M. Akstulewicz i 1:00 p.m. East Haddam, CT perience and the effectiveness of plant corrective actions 6/4/86 50-424 Rm. P-422 Discuss the location of welded NRC/ Southern Co. M. A. Miller

! 8:30 a.m. 50-425 Phillips Bldg. attachments with respect to Services / Georgia i arbitrary intermediate pipe Power Company /

i break locations and the Bechtel applicant's analysis 6/4/86 50-267 Rm.(TBA) Discuss licensing status of NRC/PSC K. L. Heitner 9:00 a.m. Phillips Bldg. Fort St. Vrain 6/4/86 50-390 Watts Bar Nuclear Site Discuss TVA's schedule for NRC/TVA T. J. Kenyon 9:00 a.m. 50-391 Sweetwater, TN activities at the Watts Bar facility 6/4/86 50-336 NRC Region I Headqtrs. Discuss the proposed NNEco NRC/NNECo D. H. Jaffe i 1:00 p.m. King of Prussia PA schedule for the Millstone 2 ILRT O

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E5 Copies of sunmaries of these meetings will be made publicly available and placed in the respective docket file (s)

[ in the NRC and local public document rooms

E ca o NRR MEETING NOTICES

• g MAY 30, 1986

. DOCKET APPLICANT /

DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 6/5/86 50-424 Rs. P-422 Discuss the Vogtle Instrumen- NRC/ Westinghouse / M. A. Miller 8:15 a.m. 50-425 Phillips Bldg. tation Technical Specification Southern Company Services /Bechtel/

Georgia Power Co.

6/5/86 50-445 Rm. P-110 Discuss Supplemental Safety NRR/ CASE A. Vietti-Cook 9:00 a.m. 50-446 Phillips Bldg. Evaluation Report No. 8 with CASE l

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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

x 3E NMSS MEETING NOTICES FOR WEEK ENDING: May 30, 1986 Divisi'on of Fuel Cycle and Material Safety -

DOCKET ATTENDEES / '

DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT 5/29/86 70-135 Silver Spring, To meet with Babcock and R. E. Cunningham, FC Crow Wilcox to discuss license

~

MD W. T. Crow, FC renewal for Apollo facility. S. Damn, B&W M. Austin, B&W 6/3/86 40-8801 St. Louis, To accompany professors fm G. LaRoche, FC LaRoche

. MO Univ. of Missouri on a site visit of the West Lake Landfill.

6/4/86 70-143 Erwin, TN To discuss status of Nuclear A. L. Soong, FC Soong Fuels Services Performance Improvement Program and other Issues.

6/9-13/86 40-8027 Gore, OK Inspection of Sequoyah Fuel J. T. Long, FC D. A. Cool Corporation. D. A. Cool, FC W. S. Pennington, FC Region Staff 6/15-19/86 70-734 Walnut Creek, To meet with Region V to W. T. Crow, FC Crow CA and Reno, discuss decommissioning of E. Shum NV . soil at GA Technologies and to attend ANS meeting.

Division of Safeguards N cne ,

Division of Waste Management None E

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May 30, 1986 e,

RII MEETING NOTICE DOCKET ATTENDEES /

NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT lDATE/ TIME 06/03/86 RII Office Enforcement Conference - Same as above Grace 10:00 am Alabama Power Company (Far'ay Facility) n E

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