ML20155K451

Weekly Info Rept for Wk Ending 860516

ML20155K451
Person / Time
Issue date:	05/21/1986
From:	Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To:
References
WIR-860516, NUDOCS 8605280340
Download: ML20155K451 (29)

Text

l o

% P b k. i May 21, 1986 l

For: The Commissioners i From: T. A. Rehm, Assistant for Operations, Office of the EDO

Subject:

WEEKLY INFORMATION REPORT - WEEK ~NDING MAY 16, 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 i

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*

Reg,ional 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) i *No input this week. , ,

W y

' lT. A. Rehm,-Asshtaff W)t for Operations Office of the Executive Director for Operations

Contact:

T. A. Rehm, EDO 492-7781 8605280340 e60521 PDR COMMS NRCC WEEKLYINFOREPT PDR

ia HIGHLIGHTS OF WEEKLY INFORMATION REPORT 1 WEEK ENDING MAY 16. 1986

! Fort St. Vrain Fort St. Vrain exceeded its 35 percent power limitation for about 45 i minutes on May 6. 1986. The plant is required by Comission Order to I limit its power level because its equipment qualification program is j incomplete.

The power excursion was caused by maintenance work on the reheat steam pressure control valve while the reactor was being operated in a load-following mode. Unexpected leakage in a hydraulic block valve

caused the control to admit more steam to the turbine. The reactor l power followed this increase in load to a peak of 42.6 percent of full j power before the operators took corrective action. ,

The licensee took the turbine off line following this event, and ,

I repaired the turbine load limiter (which had been out of service for 1 about two weeks). This was reset for 34 percent of full power before l operations were resumed.

Severe Accident Risk Assessment i The RES staff and supporting contractors are currently engaged in the reevalua-i tion of the risk of six reference LWRs. This reevaluation is currently being .

j used to support NRR's review of IDCOR submittals. In addition, it will support j the staff report NUREG-1150, which is intended to provide guidance to decision-l makers as to the appropriate role of information on core melt frequency.

j containment performance, source terms, and risk in making severe accident

decisions.

! An ACRS subcomittee letter was sent to the Comittee containing a number of .

l comments on the NUREG-1150 presentation given at Sandia National Laboratory on i May 1. 1986. RES staff is in the process of assessing the coments. No new i

! ma.jor problems were identified, but it is clear that RES may not be able to <

respond (in draft NUREG-1150) to all of the issues raised. Changes to draft

• l 1

NUREG-1150 that require revised calculations of risk likely cannot be I j accomodated unless the publication date is slipped.

LLW Host State Governors' Letters to Governors of States Regarding the l First Milestone of the Low-Level Radioactive Waste Policy Amendments l Act of 1985 4

Governors Riley, Gardner and Bryan (South Carolina. Washington, and Nevada.

l respectively) who host currently operating LLW disposal facilities wrote to several Governors of States regarding the July 1.1986, milestone of the Low-Level Radioactive Waste Policy Amendnents Act of 1985. In the letter

, dated April 21,1986, the Governors state that "it is the intention of each

! of our States to impose the penalty surcharge provided in the Act until i such time as your State has complied with the milestone." The States can i' satisfy the milestone by ratifying compact legislation, or certifying the

' intent to develop a site for the disposal of LLW or by entering an agreement with the compact comission of a region in which a disposal facility 's located The penalties that (provided would take the agreement effect are an has the approval additional of cubic

$10 per the host footState).

of l LLW from July 1 - December 31,1986, and denial of access to the three j operating sites starting January 1.1987. This letter was sent to Maine.

Massachusetts. New Hampshire. New York. Rhode Island. Vemont. District of Columbia, and Puerto Rico. All other States not in the Scutheast. Northwest, j and Rocky Mountain Compacts received a different letter asking for docu-mentation to demonstrate that they are in compliance with the July 1, 1986 milestone. gg 16 W

1 i

l OFFICE OF ADMINISTRATION 4

Week Ending May 16, 1986 ADMINISTRATION OF THE FREEDOM OF INFORMATION ACT STAT,US OF REQUESTS Initial. Appeal of Request Initial Decision r '

Carryovers, 1985 181 15 Received 1986 344 76 Granted 227 18 Denied 65 10 Pending 233 53 ACTIONS THIS WEEK Received (Anindividual Requests all records rel'ated to his cc'mplaint against the Arizona Public Service Company regarding the Palo requesting) information Verde nuclear power plant.

(86-329)

Ophelia G. Williams, Requests copies of " Safety Development Program for J/R/A Associates Water-Cooled Reactors," Quarterly Report Nos. 8, 13, (86-330) and.14.

Stevi Stephens, Requests two categories of records regarding the Wolf Nuclear Awareness ~ -Creek nuclear power plant.

Network (86-331)

Steven Aftergood, Requests four categories of records related to the Committee to April 22-24, 1986, meeting of the Interagency Nuclear Bridge the Gap Safety Review Panel in Germantown, Maryland, which was (86-332) attended by NMSS representatives.

Kathleen Brann Requests the location of the radioactive waste sites in (86-333) Long Island, New York, and Maine.

(Anindividual Requests copies of the 01 report concerning allegation RI-84-A-0086 regarding the Nine Mile Point nuclear power requesting information ) plant and the transcript of his testimony concerning said (86-334) allegation.

CONTACT: Donnie H. Grimsley 492-7211 ENCLOSURE A WAY 161986 s o y 1 .-

2 Received, Cont'd Jack Taylor, Requests six categories of records regarding the Dallas Times Soviet Union's Chernobyl accident, Soviet reactors, Herald and similarly designed reactors.

(86-335)

Jack Taylor, Requests two categories of records regarding the Soviet Dallas Times Union's nuclear industry and the Chernobyl accident.

Herald (86-336)

(NRCemployee)- Requests three categories of records regarding Vacancy (86-337) Announcement No. 86-0666-5.

~

James H. Shumock, Requests releasable records related to the successful Thompson bidder under RFP RS-RGl-86-311 and the names of the four Engineering companies submitting proposals under this RFP. '

Testing, Inc.

(86-338)

Thomas W. Hurley Requests records describing amendments to License No.

(86-339) 04-19644-01, Radiation Sterlizers, Inc., Schaumburg, Illinois, submitted after July 1,1985, and copies of inspection reports for 1985 and 1986.

Stevi Stephens, Requests copies of the back-up documentation related to Nuclear Awareness the Special Inspection of the Quality First Program Network conducted May 27-31, 1985, including inspection report (86-340) No.50-482/85-28 and records generated subsequent to the inspection report.

Jim Pedro,

~

Requests a copy of " Visual Weld Acceptance Criteria NUS Corporation for AWS Structural Welding at Nuclear Power Plant,"

(86-341) NCIG-01, submitted by NCIG on December 14, 1984.

Roberto Rivera, Requests information regarding possible NRC contracts Roberto Rivera with CPA firms in Puerto Rico or the U.S. Virgin

& Co. .

Islands.

(86-342)

Jack Taylor, Requests five categories of records regarding the Soviet Dallas Times Union's nuclear industry, the accident at the Chernobyl Herald plant, and similarly designed reactors.

(86-343)

Stevi Stephens, Requests all records related to any communication Nuclear Awareness between the NRC and the Department of Justice regarding Network allegations, investigations or reports of criminal (86-344) activity or misconduct by any person associated with the construction, licensing, or operation of the Wolf Creek nuclear power plant.

(NRCemployee) APPEAL TO THE COMMISSION for the release of denied (86-A-76-86-229) records regarding an 0IA investigation.

ENCLOSURE A HAY 18195 i

3

• Received, Cont'd Lynne Bernabei, APPEAL TO THE COMMISSION AND THE ED0 for the lack of Newman & Owens response to a request for records related to the (86-A-73-86-205) investigations by the Quality Technology Corporation of allegations by a named individual of harassment and safety problems at TVA nuclear power plants.

(NRCemployee) APPEAL TO THE COPtilSSION for the lack of response to (86-A-74-86-264) requests for records regarding an OIA investigation.

(86-A-75-86-286)

Stevi Stephens, APPEAL TO THE COMMISSION for the release of one denied Nuclear Awareness record regarding a request for records within the OI Network cases regarding investigations at the Wolf Creek nuclear (86-A-76-86-59) power plant which have occurred or been closed within the time frame of August 20, 1985, and January 29, 1986, and Quality First files related to Wolf Creek.

Granted Gregory A. Holmes, In response to a request for records from Harold Denton's MHB Technical chron and reading files from January 1, 1984, to the Associates present that concern the Diablo Canyon nuclear power plant, (86-148) informed the requester that the NRC has no records subject to this request.

Robert M. Rader, In response to a request for records relating to any Conner & request or proposal by the State of Illinois pertaining Wetterhahn, P.C. to agreement state status, made available eight records.

(86-247) Informed the requester that additional records subject to his request are already available at the PDR.

Tom Carpenter, In response to a request for 11 categories of records Government relating to the RMI Company Extrusion Plant located near  !

Accountability Ashtabula, Ohio, made available 22 records.

Project (86-271)

Jim Pedro, In response to a request for copies of enclosures 1 and NUS Corporation 2 to a September 30, 1976, letter regarding fire protection (86-304) at the Surry nuclear power plant, informed the requester that the requested records are already available at the PDR.

Jim Pedro, In response to a request for the monthly status reports NUS Corporation on plant specific backfitting activities for October 1985 (86-309) through March 1986, made available one record. Informed the requester that status reports were not prepared for l the period of November 1985 through March 1986.

MAY 161906 ENCLOSURE A

4 Granted, Cont'd John Goddard, In response to a request for a list of radioactive Rocky Mountain material licensees in Wyoming and Montana, made Medical Physics, available a copy of the requested record.

Inc.

(86-313)

Denied Peter C. Hearn, In response to a request for the names of all applicants NTEU Steward for Vacancy Announcement No. 86-0716-5, denied portions (86-224) of one record, release of which would constitute a clearly unwarranted invasion of personal privacy.

Albert V. Carr, In response to an APPEAL TO THE ED0 for the release of Duke Power Company one denied record and the withheld portions of one (86-A-14-85-584) record, regarding a request for records related to Enforcement Action No. EA-84-93 on the Catawba nuclear power plant, made available portions of one record and continued to deny the remaining portions of the other record, release of which would adversely affect the agency's deliberative process.

ENCLOSURE A MAY 161996

WEEKLY INFORMATION REPORT DIVISION OF CONTRACTS WEEK ENDING MAY 16, 1986 RFP ISSUED RFP No.: RS-0RM-86-261

Title:

" Engineering Cost Analyses of Proposed Changes In NRC Requirements"

Description:

Services for engineering cost analyses to identify, derive and analyze the engineering costs of proposed changes in NRC regulatory requirements.

Period of Performance: 30 months Sponsor: Office of Resource Managenent Status: RFP issued on May 15, 1986. Proposals due June 17, 1986.

PROPOSAL UNDER EVALUATION RFP No.: RS-01E-E6-155

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: 36 months Sponsor: Office of Inspection & Enforcement Status: The competitive range has been established and negotiations are scheduled for June 3, 1986. -

CONTRACT AWARDED l

RFP No.: RS-ADM-86-250

Title:

Course, "NRC: What It Is and What It Does"

Description:

Presentation and development of material for the above course to be presented in Bethesda, Maryland and the regions.

Period of Performance: Two years Sponsor: ' Office of Administration Status: A Fixed Price Indefinite Quantity type Contract No. NRC-10-86-250 was awarded to The Graduate School, USDA in the amount of $66,720 effective May 15, 1986.

ADMINISTRATIVE MATTERS As previously reported in the Weekly Information Report for the week ending April 25, 1986, the Contracting Officer forwarded a letter to the Small Business Administration (SBA) protesting the small business representation made by Advanced Computer Environmental Systems Support, Inc. (ACESS) under Solicitation No.

RS-ADM-86-218. Based on a review of all relevant documentation, SBA has determined that the products offered by ACESS are domestic end items as required by the solicitation. By letter dated May 7, 1986, SBA advised that ACESS, Inc. is a small business and may be considered for award.

ENCLOSURE A MAY 161RR5

l We:kly Infcrmation Report )

i Division of Contracts .

ADMINISTRATIVE MATTERS (cont'd)

Contract No. NRC-17-80-448-01 with International Verbatim Reporters Inc. (IVRI) for stenographic reporting services was terminated for default effective May 3,1980. On May 30,1980, IVRI submitted a claim to the U. S. Small Claims Court against the NRC in the amount of $337,072.89 for breach of contract and wrongful termination. In a decision filed March 26, 1986, the Court found that the NRC acted within the bounds of propriety and that the termination for default was proper. The NRC is now seeking reprocurement costs in the amount of $306,733.40.

9 e

1 i

E!! CLOSURE A MAY 161986 l

0FFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending May 16, 1986 l l

River Bend Station I At 10:40 p.m. CDT May 7, 1986 Gulf State Utilities raised the power level of River Bend Station to 100% of rated power for the first time.  !

Gulf States Utilities expects to conduct further start up tests near '

this power level over the next several weeks.

Limerick On May 7, 1986, the Appeal Board issued its Decision (ALAB-836) on the Licensing Board's Third Partial Initial Decision (PID) concerning offsite emergency planning. Actions for the Board and NRR are identified in the Decision.

The Licensing Board's third PID is reversed insofar as it finds reasonable assurance of the availability of an adequate number of bus drivers to evacuate students in two school districts; accordingly this matter is remanded for prompt action by the Licensing Board.

Otherwise, the Licensing Board's third PID is affirmed subject to the following license condition: the Director of NRR is to verify the expeditious establishment of additional traffic control measures in the area of Route 100 and the Downington interchange of the Pennsylvania Turnpike.

The plant is currently shutdown for a six-week surveillance and maintenance outage; this outage is expected to continue until mid-June.

Fort St. Vrain Fort St. Vrain exceeded its 35 percent power limitation for about 45 minutes on May 6, 1986. The plant is required by Consnission Order to limit its power level because its equipment qualification program is incomplete.

The power excursion was caused by maintenance work on the reheat steam pressure control valve while the reactor was being operated in a load-following mode. Unexpected leakage in a hydraulic block valve caused the control to admit more steam to the turbine. The reactor power followed this increase in load to a peak of 42.6 percent of full power before the operators took corrective action.

The licensee took the turbine off line following this event, and repaired the turbine load limiter (which had been out of service for about two weeks). This was reset for 34 percent of full power before operations were resumed. ENCLOSURE B MAY 161986

Pilgrim Nuclear Power Station The Pilgrim Station has been shutdown since April 11 to correct equipment problems: (1) Inspection of the MSIV's discovered that all but one of the pilot poppets were partially unscrewed or entirely separated from the valve stems due to ineffective set screws (this was a new design installed during the last refueling outage), (2) During the shutdown procedure, spurious operation of the MSIV's had resulted from changing the mode switch position from "run" to "startup" at less than 20% power; however, nothing improper was discovered during

. extensive functional and continuity testing of the mode switch (BECo will probably replace the SB-1 with an SB-9, as recommended by GE), (3)

Annunciation alarms of high pressure on the low pressure RHR piping frequently occurred due to leakage through a check valve and one or both motor operated valves in the "B" RHR/LPCI line. Tests have established that water at 1000 psig leaks through the three valves in series at approximately 0.57 gpm (an orifice may be installed on the low pressure side to provide a controlled leak to the torus, which will minimize nuisance alarms).

Boston Edison will attempt to resolve all of the above problems in time to start up prior to May 15 when its contract with the union expires.

Authorization to restart must be obtained from the NRC.

Browns Ferry Nuclear Plant Units 1, 2 & 3 A fire broke out in one cooling tower (#4 of 6) at about 2:15 p.m.

(EDT) on Saturday May 10, 1986 at the Browns Ferry site. No one was injured. No safety related equipment was affected. All three units have been shutdown over one year. Units 1 and 2 are defueled. The tower is between 1/4 and 1/2 mile from the plant reactor buildings.

The Browns Ferry fire brigade was assisted by two off-site fire departments with which TVA has contract agreements to assist if needed. The fire was extinguished at 4:08 p.m.

A special group has been appointed by TVA to investigate the cause of the fire. One theory is that the fire may have been ignited by a spark from a lift pump motor which was being started at the time the fire began. The pump was being used to wet down the tower, a task which is performed weekly.

McGuire Units 1 and 2 Today the Commission issued license amendments on McGuire Units 1 and 2 modifying the technical specifications to provide for operation at up to full power with the Upper Head Injection System either (1) fully operational, (2) isolated or (3) physically removed.

ENCLOSURE B MAY 16198E

~

ANO-2 The staff has been informed by the licensee that there might be demonstrations by a group called " NATIONAL C0ALITION AGAINST NUCLEAR POWER" on May 24, 1986. It appears that these demonstrations would take place around as many as 30 nuclear power plants including ANO.

The above information is based on a story without confirmation at this time and it will be updated as more information becomes available.

Limerick On May 12, 1986, the Appeal Board dismissed the appeal of Mr. R.

Anthony of the Licensing Board's denial and dismissal of his petitions concerning License Amendments nos. 1 and 2. Those amendments involve a one-time-only extension of the interval between containment isolation valve surveillance leakrate tests. The appeal was dismissed because the issues sought to be raised by Mr. Anthony are now moot. The plant was shut down by the licensee on May 2, 1986, for a scheduled surveillance testing and maintenance outage, which was the relief sought by Mr. Anthony.

Joseph M. Farley, Unit 2 On May 12, 1986 Farley 2 began a return to power after a scheduled 35-day refueling and maintenance outage which started on April 5, 1986.

During the outage the following significant work was accomplished by Alabama Power Company:

Eddy current tests of 100% of the remaining active tubes (9859) in the three steam generators (SGs) were completed. Seventy tubes were plugged. The number of tubes plugged is below the 5%

approved limit.

Anti-vibration bar (AVB) modifications (in the U-bend area of the tubes) were completed in SG-A and SG-B. This AVB design modification doubles the original tube contact area of the bars to reduce impact-wear tube degradation'.

All secondary system feedwater heaters were replaced with heaters having stainless steel tubes instead of copper alloy tubes to eliminate copper in sludge of the secondary system. l i

ENCLOSURE B MAY 161986 l

I NRC TMI-2 CLEANUP PROJECT DIRECTORATE WEEKLY STATUS REPORT WEEK ENDING MAY 16, 1986  :

1. DEFUELING

- No core defueling occurred during this week. The number of canisters transferred to the fuel pool remains at 42.

- Biocide addition to the RCS and hydrolancing of the reactor vessel components has been completed. Letdown and refill of the RCS is in progress. Four batches will be letdown in which about 15,000 i gallons of water will be drained and then replaced with clean barated water treated with hydrogen peroxide. Draining of 15,000 gallons of water will leave the RCS level at about elevation 310'8" which is 21 ft. above the top of the vessel flange.

- On may 12, 1986 during operations supporting rotation of the rotating work platform the trolley on the number one jib crane disengaged and fell into the reactor vessel. An operator was struck by a portion of the falling apparatus and received a scalp laceration. Approximately one half of the trolley was recovered from the vessel and examined to determine the failure mechanism.

The trolley on the number one jib crane has been replaced with another of a different design. The number two jib crane which still has the original design trolley has been inspected. No deficiencies were observed. It remains out of service pending completion of licensee investigation,. review, and modification.

2. PLANT STATUS

- The reactor remains in long term cold shutdown, vented to atmosphere. Core cooling is by natural heat loss to ambient building atmosphere. The average incore thermocouple reading is 99 F. Water visibility is approximately one foot.

- The airborne radioactivity on the defueling platform is about 7.0 E-7 uCi/cc Tritium and 2.6 E-12 uC1/cc particulates, predominately Cesium-137. The platform is mounted above the modified internals ENCLOSURE B i

indexing fixture which is mounted on the reactor vessel flange.

These provide water coverage of 151 feet over the core region.

3. WASTE MANAGEMENT

- The Submerged Demineralizer System (SDS) has processed 71,238 gallons of batch S-131 from "B" Reactor Coolant Bleed Tank. The SDS total to date is 3,954,097 gallons.

- EPICOR II has processed batch 287; 10,710 gallons from the SDS monitor tanks. EPICOR II has processed 2,925,820 gallons to date.

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.

- TMI water samples taken by EPA at the plant discharge (includes TMI-1 and TMI-2) to the river consisted of seven daily composite samples taken from April 26 - May 3, 1986. A gamma scan detected no reactor related activity above the lower limit detectability.

l The Lancaster water sample taken at the water works intake and analyzed by EPA consisted of a seven day composited sample taken from April 26 - May 3, 1986. A gamma scan detected no reactor related radioactivity.

The NRC outdoor airborne particulate sampler at the TMI site collected a sample between May 8 - 15, 1986. The results were not available and will be reported in next weeks status report.

5. AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES j A robot entry was made into the highly contaminated Seal Injection Valve Room on the 281' elevation of the Auxiliary Building. Gama dose rates up to 300 R/hr at hot spots and general area dose rates ranging from 30 - 75 R/hr were observed. All operations were remotely controlled from outside the room. The beta component has not yet been determined.

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

7. NRC EVALUATIONS IN PROGRESS Technical Specification Change Request number 49, and 51.

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

Core Stratification Safety Evaluation (Revision 3).

Solid Waste Facility Technical Evaluation Report.

MAY 161986 ENCLOSURE B

- Reactor Building Sump Criticality Safety Evaluation Report.

- Canister Handling and Preparation for Shipment Safety Evaluation Report.

- Defueling Canister Technical Evaluation Report, Revision 2.

.)

p i

gay 161986 ENCLOSURE B

OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending May 16, 1986 Near-Term NRC Actions Under the NWPA 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-86-927 was submitted to the Commission in late March 1986, for approval and publication in May 1986.

Section: 114(e)(2) of NWPA: Federal Agency Reporting Requirements Status: With the issuance of the DOE 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 final PDS, or fails to comply, is required to submit a report to the Secretary of Energy and to Congress explaining the reason for such actual or potential noncompliance.

In the final PDS, NRC is scheduled to " Issue Proposed Amendment to conform 10 CFR Part 60 to EPA Standards" in March 1986. NRC is.

planning on issuing this cmendment in early May 1986 [See Section 121(a)]. ,

Section: 141(d) of NWPA: Licensing of MRS Status: NRC has developed revisions to 10 CFR Part 72 to provide the licensing framework for the MRS, should it be authorized by ,

Congress. j l

Action The Staff Requirements memo was received by tt-e staff on i April 21, 1986, and the proposed rule is being prepared for publication in the Federal Register.

Section: 306 of NWPA: Regulations for Training of Power Plant Personnel Status: The final rulemaking on Part 55 and three associated regulatory l guides (SECY-86-123) concerning regulations for Training of Power i Plant personnel is currently awaiting OGC comments on backfitting. i Cocmission approval is expected in early June.

ENCLOSURE C

f I

Near-Term DOE Actions of Interest May 1986 - Issue Notice of Proposed Rulemaking for Defense Waste Fee May 1986 - DOE to issue final five Environmental Assessments for first repository May 1986 - DOE to nominate and recommend candidate sites for site characterization May 1986 - Secretary makes a Preliminary Determination on site suitability for a repository June 1986 - DOE to issue Final Transportation Institutional Plan Near-Term NRC Actions Under the LLEWPAA Section: 10 of LLRWPAA: Exemption of specific waste streams from regulation.

Provision: By July 1986 NRC must establish standards, procedures, and technical capability to act upon petitions to exempt specific waste streams from NRC regulations.

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

Nuclear Fuel Services, Inc., Erwin, Tennessee During the period May 5-9, 1986, an NMSS organized team conducted a Nuclear Criticality Safety (NCS) appraisal at the Erwin facility. The team consisted of members from NMSS, Region II, and an ORAU consultant. The appraisal included management, management functions, NCS evaluations, and technical and administra-tive in plant practices.

ENCLOSURE C MAY 161996

Office of Inspection and Enforcement Items of Interest Week Ending May 16, 1986

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

a. EN 85-79A - An Order Imposing Civil Monetary Penalty was issued to Exam Company (Tulsa, OK) in the amount of $5,000. This action was based on the failure to perform surveys after exposure and the failure to follow operating and emergency procedures,

b. EN 86 A Notice of Violation and Proposed Imposition of Civil Penalty was issued to Portland General Electric Company (Trojan) in the amount of $80,000.

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

a. PNO-II-86-33, Duke Power Company (Catawba 2), Initial Criticality,

b. PN0-II-86-34, Tennessee Valley Authority (Browns Ferry), Cooling Tower Destroyed by Fire.

c. PNO-II-86-35, Virginia Electric & Power Company (Surry 1), Partial Loss of DC Power and Safety Injection.

d. PN0-III-86-41, Commonwealth Edison Company (Zion 2), Shutdown to Repair Check Valve.

e. PN0-III-86-42,WisconsinPublicServiceCorporation(Kewaunee),

, Inadvertent Weapon Discharge.

f. PNO-III-86-43, Dairyland Power Cooperative (LACBWR), Smoking Insula-tion in Containment,

g. PNO-III-86-45, Kerr-McGee Chemical Company (West Chicago, IL), Forest Preserve Closes River Bank Because of Possible Thorium Contamination.

. h. PNO-III-86-46, Coninonwealth Edison Company (La Salle 2), Shutdown for l More Than 48 Hours.

- 1. PNO-IV-86-17, Arkansas Power and Light Conipany (ANO 1), Potential Media Interest--Citizens' Hearing.

ENCLOSURE D

2

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

a. IE Information Notice No. 86-34, Improper Assembly Material Selection and Test of Valves and Their Actuators was issued to all nuclear reactor facilities holding an operating license or a construction permit.

b. IE Information Notice No. 86-35, Fire in Compressible Material at Dresden Unit 3, was issued to all nuclear power reactor facilities holding an operating license or a construction permit.

c. IE Information Notice No. 86-36, Change in NRC Practice Regarding Issuance of Confinning Letters to Principal Contractors was issued to all nuclear power reactors holding an operating license or a construc-tion permit.

d. IE Information Notice No. 86-37, Degradation of Station Batteries was issued to all nuclear power reactors holding an operating license or a construction permit.

4. Other Items

a. Senior Management Meetings Deputy Director, IE, visited the Summer facility this week and participated in a management meeting in Region II.

b. Operations Center (1) The NRC Chernobyl Incident Tracking Team is continuing to coordi-nate the NRC's support to EPA through the Operations Center. Pre-parations for the ACRS and Connission briefings were coordinated throught the Center. Radiological measurements continue to be received, entered, and plotted by fractions of EPA Protective Action Guidelines (PAGs) by day.

(2) The Director, Division of Emergency Preparedness and Engineering Response and an Incident Response Branch staff member attended meetings in Chicago on May 12, 13 for the purpose of organizing the Federal / State / Utility planning effort for the next Federal Field Exercise (FFE) scheduled for the summer of 1986. It is expected that the exercise will involve the Zion facility and various agencies of the States of Wisconsin and Illinois in I addition to Commonwealth Edison and the 11 other federal agencies.

c. Vendor Program The following Vendor Program Branch inspections were conducted this week:

ENCLOSURE D MAY 161986

~

3 l

l i

(1) WFI Nuclear Products, Houston, TX - to evaluate control of nonconformances as identified in a Part 21 report, review implementation of the QA program for the manufacture of fittings and flanges, and review an allegation pertaining to welding.

(2) Consolidated Edison Company and Indian Point Unit 2, Buchanan, NY - to review program and its implementation to determine conformance to the requirements of 10 CFR 50.49.

(3) Westinghouse Electric Corporation, Control Equipment Group, Beaver, PA - to obtain additional information on the failures of molded case circuit breakers LBB 22250 at Peach Bottom 2 &

3 and Limerick 1.

(4) Golden Gate Forge and Flange, San Francisco, CA - followup on Part 21 report regarding deficient records for flanges supplied to D.C. Cook and Midland.

d. TVA Activities (1) Members of the Vendor Program Branch and the Engineering and Generic Communications Branch are participating on an NRC task force evaluating TVA allegations.

(2) Two Quality Assurance Branch staff members are attending a TVA meeting on Sequoyah design control issues.

! e. Safety System Functional Inspections (SSFI) t l The full SSFI team inspection is scheduled to begin their onsite inspection at Oconee the week of May 19, 1986. The exit is planned for June 6, 1986.

f. Safety System Outage Modification Inspection (SSOMI)

The Dresden 3 SSOMI team has completed the first half of the installation and testing part of the inspection. The team plans to return to the site in mid-June for the final part of the inspection,

g. Comanche Peak Activities 2

(1) Two Quality Assurance Branch staff members are at Comanche Peak with Region IV personnel to review implementation of the CPRT QA program.

(2) A Quality Assurance Branch staff member is at Comanche Peak with construction support to inspect implementation of the TERA design review efforts. i MAY 161986  !

ENCLOSURE D l

4 i

j h. Generic Issues At Trojan, the large hydraulic snubbers at the top of the steam generators apparently locked up in normal service due to material from degraded / aged seals clogging the bleed paths. The licensee is performing stress analyses intended to demonstrate that the resultant stresses on the reactor coolant system were acceptable. NRR and Region V are evaluating the licensee's actions. IE is evaluating generic reliability problems of several kinds in this service.

i. Emergency Preparedness (1) The Deputy Director, Division of Emergency Preparedness and Engineering Response (DEPER) met with the staff of Congressman Robert C. Smith, New Hampshire, to discuss the status of Seabrook. The Congressman represents the area in which the Seabrook site is located and wanted up-to-date information on the NRC licensing process with specific emphasis on emergency planning. Representatives of CA and NRR participated in the briefing.

(2) Representatives of the GA0 met with the Deputy Director, DEPER to discuss the status of Shoreham. This meeting was requested by GA0 in order to provide them sufficient background informa-tion for a meeting scheduled with Senator Moynihan, New York, during the week of May 12, 1986. The GA0 was also meeting, in parallel, with FEMA on the same subject.

(3) In response to a re' quest from Congressman Markey, the Emergency Preparedness Branch (EPB) provided information on the use of potassium, iodine (KI). EPB, in conjunction with DOE, also  ;

developed responses for Congress on several other questions related to the Chernobyl accident.

(4) EPB coordinated with FEMA and NRC Region IV to obtain informa-tion related to an upcoming remedial exercise regarding the alert and notification system for a recreational area within the Cooper emergency planning zone.

ENCLOSURE D g g

0FFICE OF NUCLEAR REGULATORY RESEARCH Items of Interest Week Ending May 16, 1986 B&W Multiloop Integral System Test (MIST) Commissioning A commissioning ceremony was held at the Babcock and Wilcox (B&W) Research Center in Alliance, Ohio for the MIST facility on Saturday, May 10, 1986. MIST is a full pressure full height volume scaled thermal hydraulic simulation of a B&W reactor. It was built under a joint arrangement with NRC, the Electric Power Research Institute, the B&W Owners Group and the B&W Company. Test data from MIST will be used to validate safety analysis codes such as NRC's TRAC code for accidents such as small break loss-of-coolant accidents and accident recovery techniques such as feed-and-bleed cooling.

The facility was completed ahead of schedule and under cost (construction cost was projected to be $12.3 million). The NRC was represented at the ceremony by staff from RES and NRR including the Director and Deputy Director of RES. Top officials from the other three participants and the local Congressman also participated in the ceremony.

Testing is beginning this month (May, 1986).

Completion of Reinforced Concrete Containment Model As part "of our Containment Research Program, a reinforced concrete scaled model (1/8th the size of a dry pressurized water reactor containment) is being constructed at Kirkland Air Force Base in Albuquerque, New Mexico. Sandia has subcontracted the United Engineers and Constructors to design and build the model. The design was completed in June 1985. The construction of the model was completed on May 15, 1986 - 3 weeks ahead of the schedule.

It is planned to perform low pressure testing, to instrument the model, to perform the structural acceptance and leakage testing and, finally, to subject it to a high pressure test. The high pressure testing is planned for early 1987.

I ENCLOSURE E MAY 16 E86

2 Publication to be Issued in the Near Future

Title:

Instruction Concerning Prenatal Radiation Exposure (Reg. Guide 8.13, Rev. 2)

Description:

This guide describes the instructions required by Section 19.12 that should be provided to workers and supervisors concerning biological risks to the embryo / fetus exposed to radiation, the recommended dose limits in Part 20, and su'ggestions for reducing the radiation exposure.

Contact:

Judith D. Foulke (301)427-4563 Recently Issued Publication Draft Regulatory Guide and Value/ Impact Statement: Proposed Revision 2 to Regulatory Guide 7.9, Standard Format and Content of Part 71 Applications for Approval of Packaging for Radioactive Material, Task FC 416-4. Comments requested by July 25, 1986.

Contact:

R.H. Odegaarden (301) 427-4122.

N LOSURE E MAY 161966

i l

3 1

i RES RULEMAKING ACTIVITIES AND RELATED AREAS ,

Severe Accident Risk Assessment

The RES staff and supporting contractors are currently engaged in the reevalua-tion of the risk of six reference LWRs. This reevaluation is currently being i used to support NRR's review of IDCOR submittals. In addition, it will support l the staff report NUREG-1150, which is intended to provide guidance to decision-makers as to the appropriate role of information on core melt frequency, containment performance, source terms, and risk in making severe accident decisions.

i An ACRS subcommittee letter was sent to the Comittee containing a number of coments on the NUREG-1150 presentation given at Sandia National Laboratory on

! May 1, 1986. RES staff is in the process of assessing the comments. No new major problems were identified, but it is clear that RES may not be able to j[ respond (in draft NUREG-1150) to all of the issues raised. Changes to draft i

NUREG-1150 that require revised calculations of risk likely cannot be j accomodated unless the publication date is slipped.

j Shipping Cask Response to Severe Transportation Accidents--Modal Study The purpose of this study is to determine 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 j when subjected to severe transportation accident environments, as well as by i assessing the likely frequency of such environments. A draft final report was j received on April 22, 1986.

k At NMSS' request, a briefing will be held at Lawrence Livermore National

! Laboratory (LLNL) on May 22, 1986.- The topic will be a discussion of

objective, approach, and results of the subject program which have been i presented in a draft final engineering report. DOE and DOT representatives are j currently planning to attend, along with representatives from RES and members

ofthepeerreviewteamfromtheDenverResearchInstitute(DRI). NMSS has also requested, and RES has agreed, that the publication of the engineering report as a NUREG/CR be deferred until the peer review by DRI is completed.

i The engineering report, including minor NRC comments, has been sent to DRI to i begin the review process. LLNL has agreed with this method of beginning the peer review process and will transmit a " clean" copy of the report, including appropriate NRC comments and LLNL corrections in mid-June to NRC and DRI.

J i

j ENCLOSURE E GAY 161986

4 Containment Performance Design Objective (CPDO) Workshop As part of the RES activity on the development of a CPD0 for possible incorporation into the Commisson's policy on safety goals, a workshop was held May 12-13 in Harpers Ferry, West Virginia. The meeting was hosted by Brookhaven National Laboratory (BNL). Sixteen invited experts with diverse backgrounds participated in the meeting and approximately 25 individuals, including NRC and BNL staff members, attended as observers. Merits and drawbacks of adding a CPD0 to the safety goals and the choice among the CPD0 options were discussed. Although no concensus was developed on these issues, general guidance for the direction of future work on the CPD0 emerged during the meeting. A verbatim record of the meeting was kept, and a highlights report will be published.

. I ENCLOSURE E MAY 161986

l ITEMS OF INTEREST OFFICE OF INTERNATIONAL PRDGRAMS WEEK ENDING MAY 16, 1986 Testing of Maanshan Repairs Continues The Taiwan Atomic Energy Council (AEC) announced Wednesday, May 14, that they have allowed the Taiwan Power Company (TPC) to roll the repaired turbine-generator at Unit 1 of the TPC's Third Nuclear Power Station (Maanshan) for further testing. The AEC has been strictly monitoring the battery of tests being conducted to check the repairs to the unit's turbine-generator system which was destroyed by a fire on July 7,1985.

Unit 1 is now expected to resume commercial operation in early June if all tests continue to run smoothly.

Visit of Korean Minister of Science and Technology On Thursday there was an interagency meeting at the State Department to discuss preparations for the upcoming visit of Hakze CHON, Korean Minister of Scie'nce and Technology. Minister Chon will be in Washington, DC, the week of June 23 to hold a number of meetings in the science and technology area. IP was asked by the State Department to arrange courtesy calls for Minister Chon with the Comission.

Foreign Visitors On Friday, May 9, a German delegation consisting of members of the RSK (the German ACRS) and GRS (Reactor Safety Comission) visited NRC for talks on radioactive waste management issues. The delegation met with the.ACRS and afterwards with the NRC staff (NMSS) to exchange views and compare approaches in the two countries.

On Monday and Tuesday Mrs. Cecile Izabel from the French Central Service for the Safety of Nuclear Installations (SCSIN) and Mr. Pierre Escalier des Orres from the French Atomic Energy Comission (CEA) met with the staff from RES and NMSS to discuss siting criteria for waste disposal and the regulation of low- and high-level waste.

On Thursday Dr. John Cullen, Chairman of the UK Health and Safety Comission, Mr. Jim Hamer, Deputy Chairman, and two officers of the British Embassy in Washington met with Chairman Palladino, Comissioners Zech, Roberts, and Bernthal and J. Shea of IP to discuss nuclear cooperation topics.

gg ENCLOSURE G J

i l

I

OFFICE OF STATE PROGRAMS ITEMS OF INTEREST WEEK ENDING MAY 16, 1986 l

LLW Host State Governors' Letters to Governors of States Regarding the First Milestone of the Low-Level Radioactive Waste Policy Amendments Act of 1985 3 Governors Riley, Gardner and Bryan (South Carolina, Washington, and Nevada, respectively) who host currently operating LLW disposal facilities wrote to several Governors of States regarding the July 1,1986, milestone of the Low-Level Radioactive Waste Policy Amendments Act of 1985. In the letter dated April 21, 1986, the Governors state that "it is the intention of each of our States to impose the penalty surcharge provided in the Act until such time as your State has complied with the milestone." The States can satisfy the milestone by ratifying compact legislation, or certifying the intent to develop a site for the disposal of LLW, or by entering an agreement with the compact conunission of a region in which a disposal facility is located The penalties that (provided wouldthe takeagreement effect arehas the approval an additional $10ofper thecubic host State).

foot of LLW from July 1 - December 31, 1986, and denial of access to the three operating sites starting January 1, 1987. This letter was sent to Maine, Massachusetts, New Hampshire, New York, Rhode Island, Vermont, District of Columbia, and Puerto Rico. All other States not in the Southeast, Northwest.

and Rocky Mountain Compacts received a different letter asking for docu-mentation to demonstrate that they are in compliance with the July 1,1986, milestone.

LLW Legislation in Maine Governor Brennan signed on April 16, 1986, LLW legislstion to provide for development of a State low-level radioactive waste facility if necessary (Public Law Chapter 708). The purpose of this legislation is to establish a program for the' safe management of LLW and to provide capacity for its disposal either within Maine or in regional facilities. Maine has not enacted any legislation to enter into a compact, but the Governor has authority to enter into such arrangements.

l g ENCLOSURE H l

t

~

NRR MEETING NOTICES

• g MAY 16, 1986 4 '

O DOCKET APPLICANT /

DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 5/19/86 50-213 Northeast Util. Office Discuss the status of NRC/NU F. Akstulewicz 1:00 p.m. Berlin, CT licensing activities including the technical specification applications for reporting re-quirements 5/20-22/86 50-213 5/20822-NU Ofc. Discuss the results of the NRC/SAI/NU F. Akstulewicz

8

30 a.m. Berlin, CT .Probabilistic Safety Study of 5/21-Haddam Neck Plant the Haddam Neck Plant East Haddam, CT l

5/21/86 - Suite 220 - B&W Ofc. Discuss B&W owners group on- NRC/B&W Owners Group W. Paulson 1:00 p.m. Woodsont Building going evaluation of the Inte-grated Control System and Non-Nuclear Instrumentation 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 j Hatch Unit 1 and 2 and the status of Hatch 1 and 2 licen-sing activities

!, .E n 5

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

i.

-. .=. _. -- -_ - __

e ,

NMSS MEETING NOTICES Division of Fuel Cycle and Material Safety EN DOCKET ATTENDEES /

NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT

%DATE/ TIME 6/15-19/86 70-734 Walnut Creek, To meet with Region V to discuss W. Crow (FC) Crow CA decomissioning of soil at GA E. Shum (FC)

Reno, NV Technologies, and to attend ANS meeting in Reno.

5/19-20/86 Project West Valley, To visit West Valley site to DOE / West Valley Clark M-32 NY observe disposal area field Reps Deering conditions and discuss develop- T. Nicholson (RES) ment of disposal methods. L. Deering (WM)

J. Grim (WM) 5/20/86 70-135 Willste Meeting with Babcock & Wilcox W. Crow (FC) Crow to discuss license renewal for S. Damn (B&W) '

the Apollo facility. M. Austin (B&W) 1 Division of Safeguards j

None Division of Waste Management None i

1 $

4 P

2

8

!5 m ,

T I

4

" May 16, 1986

• RII MEETING NOTICE .

R DOCKET ATTENDEES /

PURPOSE APPLICANT NRC CONTACT DATE/ TIME NUMBER LOCATION RII Office Supervising Human Resources Selected Managers Maley 05/19-23/86 and RII Staff Members Course being given in RII RII Office Meeting with representatives Licensee and' Selected Gibson 05/20/86 of FP8L (Turkey Point) on RII Staff Members 11:30 am diesel generator problems Lynchburg, VA Discussion of NRC Observa- Licensee and Selected Stohr 05/28/86 RII Staff Members 9:00 am tion of Licensee's Activities regarding the Regulatory Process Browns Ferry Enforcement Same as above Reyes 9:00 am RII Office Conference RII Office Crystal River SALP Selected HQs and RII Reyes 05/29/86 8:30 am Board Meeting 05/29-30/86 Licensee, Regional Reyes Miami, FL Turkey Point Performance Enhancement Program Meeting Administrator and selected RII Staff '

Members 05/30/86 RII Office Sequoyah Enforcement Licensee arid Selected Reyes 10:00 am Conference Region II Staff Members P

8

!5 m

--_--_ _ -___ __ _