ML20199L311

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Weekly Info Rept for Wk Ending 860328
ML20199L311
Person / Time
Issue date: 04/07/1986
From: Rehm T
NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To:
References
WIR-860328, NUDOCS 8604100347
Download: ML20199L311 (43)


Text

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s April 7,1986 For: The Commissioners From: T. A. Rehm, Assistant for Operations, Office of the EDO

Subject:

WEEKLY INFORMATION REPORT - WEEK ENDING MARCH 28, 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 8 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 Comission 0 Meeting Notices P Proprietary or Other Sensitive Information (Not for Q external distribution)

  • No input this week. , ,

y 7' \ n-

/T. A. Re for Operations Office of the Executive Director for Operations

Contact:

T. A. Rehm, ED0 0604100347 060407 492-7781 PDR coMMs NRec WEEKLYINFOREPT PDR

l s

HIGHLIGHTS OF WEEKLY INFORMATION REPORT WEEK ENDING MARCH 28, 1986 Fermi-2  :

1986 the load-side breaker from the reactor protection On March system bus 16,A" to the RPS "A" logic circuits failed to trip. When -

transferring from the M-G set to the alternate power source. The -

breaker should have tripped on the somentary loss of voltage. Upon a local manual attempt to trip the breaker, it responded in about 10 seconds. Upon the next attempt, the breaker failed to trip at all.

The licensee agreed to " quarantine" the failed breaker, pending the development of agreed upon troubleshooting.

' Subsequently, the licensee has agreed to conduct a laboratory failure analysis of the failed breaker. It appears at this time that this is a plant-specific situation.

5 Federally Funded Research and Development Center (FFRDC)

On March 11 and If., 1986, NRC published a " Notice of Intent" in the Federal Reatster and Commerce Business Daily announcing that NRC is considering the establishment of an FFADC for waste management technical assistance and t research. An FFRDC is being considered by NRC as a potential solution to the problems of conflict of interest and long-term continuity with respect to

. contractual work related to the Nuclear Waste Policy Act of 1982. The Notice of Intent announced the availability of a draft solicitation package and requested public comments. Comments will be analyzed and made aval.lable to the

Commission before it votes on issuance of a formal, competitive solicitation for proposals. '

i i

1 MAR 0 : 1985 '

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

i OFFICE OF ADMINISTRATION Week Ending March 28, 1986 -

ADMINISTRATION OF THE FREEDOM OF INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Carryovers,1985 181 15 Received, 1986 228 46 Granted 142 12 Denied 41 2 Pending 226 47 ACTIONS THIS WEEK Received Joshua Gordon, Requests records that list or describe injuries and deaths Critical Mass at any NRC-licensed facility or at any other facility used (86-199) in the nuclear fuel cycle, and all records that list or describe injuries and deaths caused by the transportation of radioactive materials.

Robert L. Williams, Requests copies of all FOIA requests within the past AMP Incorporated five years.

(86-200)

Billie P. Garde, Requests all records generated or prepared by Victor Stello Government beginning with his appointment as Acting Executive Accountability Director for Operations.

Project (86-201)

Billie P. Garde, Requests all records related to O! investigations of the Government Fermi nuclear power plant.

Accountability Project (86-202)

Lynn Connor, Requests copies of the January 9, 1985, memo between Doc-Search Messrs. Eisenhut and Denton and any subsequent staff Associates memo dealing with uprating (stretch power).

(86-203)

Lynn Mathis, Requests all inspection records on the River Bend nuclear Guaranty power plant.

Broadcasting Corp.

(86-204)

CONTACT: Donnie H. Grimsley 492-7211 ENCLOSURE A f.MR E C03

2 Received, Cont'd Lynn Bernabei, Requests records related to investigations and Newman & Owens investigative reports by the Quality Technology (86-205) Corporation of allegations by Mr. James Jones of harassment and safety problems at TVA plants, records submitted by TVA in response or rebuttal to those reports, records related to NRC's response to the problems identified in those reports, and records related to NRC investigations into harassment and intimidation of employees at the TVA plants.

Steven C. Sholly, Requests five categories of records related to the MHB Technical recent reorganization of NRR and past and current Associates filing systems.

(86-206)

Cathleen M. Roughan, Requests (1) a litt of licensees authorized to possess Tech / Ops, Inc. Gadolinium-153 for bone-scanning use; (2) records or (86-207) drawings for Amersham Corporation's sealed source model N). GDC.CY1 for Gd-153; and (3) records or drawings for New England Nuclear's sealed source model No. NER 430 and NER 431 for Gd-153.

Billie P. Garde, Requetts all records related to any information known Government to the NRC about potential sabotage at the Comanche Accountability Peak nuclear power plant.

Project (86-208)

Billie P. Garde, Requests all records generated or prepar d by Victor Stello Government beginning with his appointment as Acting Executive Accountability Director.

Project (86-209)

Kate Duffy, Requests copies of the synopsis of the three investigations Kansas City conducted in 1985 by OI into allegations of possible Business Journal safety violations at the Wolf Creek nuclear power plant.

(86-210)

Billie P. Garde, Requests copies of all completed O! investigation of the Government Waterford plant, specifically reports into harassment Accountability and intimidation, records falsification, and material Project false statements made by Waterford officials.

(86-211)

Billie P. Garde, Requests copies of all records from March 6, 1984, to the Government present pertaining to plans and proposals for OI and OIA Accountability to be combined.

Project (86-212)

ENCLOSURE A

%R 2 ' $35

3 Received Cont'd Billie P. Garde, Requests all records from October 1,1984, to the Government present related to the reports listed in Board Accountability Notification No.84-149 Project (86-213)

Billie P. Garde, Requests all records from Mrach 6,1985, to the present Government related to inspection reports 50-445/84-32 and 50-446/

Accountability 84-11 regarding the Comanche Peak nuclear power plant.

Project (86-214)

Billie P. Garde, Requests copies of all records related to the September 19, Government 1984, proposed Manual Chapter 0571, " Management of Accountability Allegations."

Project (86-215)

Billie P. Garde, Requests copies of all records regarding IE Infonnation Government Notice 85-66 Accountability Project (86-216)

Billie P. Garde, Requests all records regarding NRC's review of the Government Comanche Peak drug abuse terminations.

Accountability Project (86-217)

Billie P. Garde, Requests all records regarding comunications generated or Government received by Victor Stello regarding the Comanche Peak Accountability nuclear power plant.

Project (86-218)

Billie P. Garde, Requests all recc.as since June 1, 1984, related to any Government comunications between any person of the Executive Branch Accountability and any NRC Comissioner, staff person working for a Project Comissioner, or any staff Project member regarding the (86-219) Comanche Peak plant.

Billie P. Garde, Requests records in connection with all information, Government provided in any form, to the DOE Nuclear Power Task Accountability Force about the Comanche Peak nuclear power plant.

Project (86-220)

James T. Tierney, Requests six categories of recnrds related to storage State of Maine of nuclear waste or spent fuel in Maine. .

(86-221)

ENCLOSURE A MAR i ' 198G s

4 Received Cont'd George R. Holeman, Requests copies of all records to and from the NRC and Yale University Mary Olson, a former Yale employee, and/or her attorneys (86-222) between May 1985, and June, 1986.

Billie P. Garde, Requests records relating to the EG&G report on Government harassment and intimidation and the EG8G/NRC contract Accountability regarding the Comanche Peak nuclear power plant.

Project (86-223)

Peter C. Hearn, Requests two categories of records related to NRC NTEU Steward Vacancy Announcement No. 86-0716-5.

(86-224)

Peter C. Hearn, Requests copies of all records used to determine the NTEU Steward classification of the 801, 830, and 840 series in NRR.

(86-225)

Richard A. Cardenas Requests a copy of License Sub-1291, Kelly Air Force (86-226) Base, San Antonio, Texas.

Jim Pedro, Requests NRR Office Letters 9, 16, 20, 25-33 and any NUS Corporation greater than 40.

(86-227)

Hennan L. Moore Requests six specified security clearance forms.

(86-228)

Stevi Stephens, APPEAL TO THE EDO for the lack of response to a request Nuclear Awareness for records within the Office of Investigation's cases Network regarding investigations which have occurred within the (86-A-33-85-600) time frame of May 1,1985 and August 27, 1985.

Billie P. Garde, APPEAL TO THE COMMISSION for the release of eight denied Government records regarding a request for records generated or Accountability prepared by Victor Stello beginning with his appointment Project as Acting Executive Director.

86-A-34-86-53 86-A-35-86-54 86-A-36-86-55 Billie P. Garde, APPEAL TO THE COMMISSION for the release of 10 denied Government records regarding a request for records relating to IE Accountability Information Notice 85-01, " Applicability of 10 CFR 21 to Project Consulting Firms Providing Training," dated December 31, (86-A-37-86-37) 1985.

Billie P. Garde, APPEAL TO THE EDO for the release of four denied records Government regarding a request for records related to the NRC Accountability staff's determination of a potential material false Project statement an U-Bolt sample, BN 85-077, that was issued (86-A-38-85-614) on August 20, 1985, in regard to the Comanche Peak nuclear 90wer plant.

ENCLOSURE A fudt 2 ; 1986

5 Billie P. Garde, APPEAL TO THE C0ttilSSION AND THE EDO for the release of Government 18 denied records regarding a request for records related Accountability to NRC Announcement No. 110. " Proper Use and Control of

, Project Telephone Services," dated November 5, 1985..

, (86-A-39-86-35)

Billie P. Garde, APPEAL TO THE EDO for the lack of response to a request Government for records regarding an inspection conducted during the Accountability period August 26-29, 1985, concerning TVEC's policies, Project procedures and implementation of the Comanche Peak site (86-A-40-86-132) Ombudsman and SAFETEAM programs.

Billie P Garde, APPEAL TO THE COMMISSION for the lack of response to a Government request for records regarding all OIA investigations 4

Accountability involving allegations of wrongdoing by NRC personnel Project connected with Region IV since 1980.

(86-A-41-86-133) i Billie P. Garde, APPEAL TO THE EDO for the lack of response to a request

Government for records regarding all audits done by OIA of 01.

j Accountability Project i

(86-A-42-86-134)

Billie P. Garde, APPEAL TO THE COMMISSION for the lack of response to a Government request for records regarding all Comission considerations Accountability regarding OI.

Project (86-A-43-86-135)

Billie P. Garde, APPEAL TO THE COMMISSION AND THE EDO for the lack of response Government to a request for all records regarding comunicatinns Accountability concerning Joseph Macktal.

Project

(86-A-44-86-157)

Stephanie A. Murphy, APPEAL TO THE E00 for the incompleteness of search for Nuclear Information records related to allegations made by Frank Peguese and Resource regarding construction defects, improper procedures.

Service poor quality assurance or other complaints about the (86-A-45-85-358) Shearon Harris nuclear power plant.

l Margaret L. Ryan, APPEAL TO THE COMMISSION for the release of denied Inside NRC notation votes by the Commission in the months of (86-A-46-85-409) January, February, March, April, and May 1985.

Granted Wendy Parker, in response to a request for copies of records The Montgomery detailing violations of NRC regulations or accidents County Sentinel involving licensees authorized to handle radioactive (86-122) or byproduct materials in Montgomery County, Maryland, since 1985, made available 19 records, fl.Ah , '.5C3 ENCLOSURE A

6 Granted, Cont'd

Gregory A. Holmes, In response to a request for copies of records from 4

MHB Technical Mr. Richard Vollmer's chron and reading files from Associates September 1,1981, through December 31, 1985, that concern (86-143) Diablo Canyon, informed tha requester that the NRC has no records subject to this request.

Bruce E. Caruthers In response to a request for copie: of the NRC Merit (86-164) Promotion Plan and amendments in effect since May 1982, made available two records.

R. Kent Edward, In response to a request for copies of any Mallinckrodt Syncor nuclear licenses which authorizes use in Illinofs, International made available 20 records.

Corporation (86-153) i Denied Tom Carpenter, In response to a request for records concerning procedures Billie P. Garde, for loading or unloading uranium fuel at Sequoyah and the i Government incident on January 4,1986, at Sequoyah, made available '

! Accountability 26 records. Informed the requester that three additional Project records subject to this request are already available at (86-7) the PDR. Denied two records in their entirety and portions of six records, release of which would cause a clearly unwarranted invasion of personal privacy.

Myron L. Scott, In response to a request for records regarding the Coalition for Combustion Engineering Auxiliary Pressurizer Spray System Responsible Energy at the Palo Verde nuclear generating station and other Education plants, and any ACRS or other discussinns pertaining to (86-45) the APSS, made available 26 records. Informed the requester that additional records subject to this request are already available at the PDR. Denied four records in their entirety, release of which would tend to inhibit the i open and frank exchange of ideas essential to the deliberative process.

i "AP. L 1005 ENCLOSURE A i '

i

WI.EKLY INe0RMATION REPORT DIVISION OF CONTRACTS WEE < ENDING MARCH 28, 1986

~

RFP ISSUED RFP No.: RS-0RM-86-263

Title:

" Conventional ADP Systems Development"

Description:

The contrector shall provide all necessary personnel, materials, -

equipnent and facilitiet to analyz?, design and develop systems (applications) using RAM 75 II and ;DMS/R data base management systems.

Period of Performance: One year Sponsor: Office of Resource Managenent Status: Closing date has been extended to April 1, 1986.

PROPOSALS UNDER EVALUATION RFP No.: RS-ADM-86-213

Title:

"Informstion Technology Services (115) Training Laboratories"

Description:

Operation and maintenance of th? ITS Trair.ing Laboratory, including the provision of ADP training to managers and other technical and nontechnical end users.

Period of Performance: 24 months Sponsor: Office of Administration Status: The competitive range has been established and negotiations are scheduled for the week of April 7, 1986.

RFP No.: RS-0RM-85-336

Title:

"ADP Information Technology Support Center"

Description:

End-user computing support services for users of NRC microcomputers and NRC users of the NIH Computer Facility.

?eriod of Performance: Two years Sponsor: Office of Resource Managenent Sta*Ls: The competitive range has been established and negotiations are scheduled for the week of April 14, 1986.

RFP Ho.: RS-ADM-86-250

Title:

Course, "NRC: What It Is and What It Does" Descript.on: 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: Negotiations completed on M5 ch 21, 1986. Best and Final offers are due on April 2, 1986.

t,3p, ; je86 ENCLOSURE A

Weekly Information Report Division of Contracts -

RFP No.: RG1-86-311

Title:

" Technical Support for Non-Destructive Examination Van"

Description:

On a task order basis, the contractor shall provide personnel with expertise in the field of non-destructive examination and use of a radiographic isotope source to perform field non-destructive examinations at nuclear power plants under construction or in operatior anywhere in the United States.

Period of Performance: 24 months Sponsor: Region I, Division of Reactor Safety Status: Second round of negotiations held March 26, 1986.

CONTRACTS AWARDED RFP No.: RS-0!E-85-156

Title:

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

Description:

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

! Period of Performance: Three years Sponsor: Office of Inspection and Enforcement Status: A Cost-Plus-Fixed-Fee Task Order type Contract No. NRC-05-86-156 was awarded to Parameter, Inc. with a ceiling amount of $2,040,000, effective March 24, 1986.

FrP No.: RS-0!E-85-158

Title:

" Technical Assistance in Developing and Implementing Programs and Procedures for Inspection of.0perating Reactors During Major Outages"

Description:

The objective of this project is to provide technical assistance to the NRC for activities pertaining to planned outages of operating reactors. This includes the development of standardized inspecticn procedures as well as providing assistance to the regional offices for conducting inspections.

Period of Performance: Three years Sponsor: Office of Inspection and Enfcreement Status: A Cost-Plus-Fixed-Fee Task Order type Contract No. NRC-05-86-158 was awarded to Parameter, Inc. with a ceiling amount of $2,100,000, effective March 24, 1986.

ENCLOSURE A il,M ., . 23

Weekly Information Report Division of Contracts .

CONTRACTS AWARDED (cont'd)

RFP No.: RS-0!E-86-170

Title:

" Assistance for Emergency Response"

Description:

Provide technical, logistical and administrative assistance for the maintenance and functioning of the NRC Headquarters Operations Center.

Period of Performance: 12 months Sponsor: Office of Inspection and Enforcement Status: A Cost-Plus-Fixed-Fee Task Order type Contract No. NRC-05-86-170 was ewarded to Comex Corp. in the amount of $212,306.00, effective March 20, 1986.

RFP No.: RS-ADM-86-214

Title:

" Management Skills for Secretarial and Clerical Staff"

Description:

The contractor shall present five independent courses to NRC's administrative assistants, secretarial and' clerical staff for enhancement of their administrative skl11s.

Period of Performance: Two years Sponsor: Office of Administration Status: A Fixed-Price Requirements type Contract No. NRC-10-86-214 was awarded to SBA/ Computer Resource Management, Inc. in the anount of $123,216.00, effective March 28, 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.

' 'b ENCLOSURE A'

. 0FFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending March 28, 1986 Fermi-2 On March system bus16;A" ' logic to the RPS "A" circuits failed to trip.1986 the load-side When breaker from the reactor p transferring from the M-G set to the alternate power source. The breaker should have tripped on the momentary loss of voltage. Upon a local manual attempt to trip the breaker, it responded in about 10 seconds. Upon the next attempt, the breaker failed to trip at all.

The licensee agreed to " quarantine" the failed breaker, pending the development of agreed upon troubleshooting.

Subsequently, the licensee has agreed to conduct a laboratory failure analysis of the failed breaker. It appears at this time that this is a plant-specific situation.

Perry Earthquake The ASLAB issued an Order dated March 20, 1986 for a hearin motion filed by Ohio Citizens for Responsible Energy (OCRE)g to admit on the the Perry earthquake as a new contention issue. The Order contains questions which the ASLAB desires the licensee and the NRC staff to address.

A prehearing conference call among all parties will be held on Friday, April 4, 1986 at which time we will identify hearing witnesses to the ASLA8, and establish schedules when written testimony will be filed and a schedule for the hearing date(s). The ASLAB expects the hearing will be convened in the Cleveland, Ohio area and last 2 to 3 days.

Millstone 3 Millstone 3 is currently operating at about 20% while slowly decreasing power in order to reduce turbine vibration.

The unit tripped on Wednesday night (March 19,1986) due to low level in a steam generator. At the time the unit was operating at about 5%

while salt deposits resulting from high winds during a storm were being washed from the main transformer insulators. Earlier the same day power was reduced from 50% to 20% to remove debris from the intake screens also caused by the storm.

OthereventswhichoccurredonMarch19wereapartialsafetyinjection which occurred when testing of the main steam valve building ventilation dampers resulted in one train of safeguards pumps start.ing; and a pressurizer pressure variation resulting from momentary opening of the pressurizer spray valves and PORV A. Both events resulted from related I & C work.

ENCLOSURE B li%R 2 01983

On Thursday night, March 20, Millstone 3 started up and power was -

increased to 50% after which excessive turbine vibration was observed.

The licensee will continue to slowly reduce power in order to reduce the vibration. If necessary the unit will be shutdown and the turbine rotated on the turning gear to correct the problem.

The licensee's response to the staff's request for information concerning Station Blackout was received on March 19, 1986, s River Bend Station On March 20, 1986, Gulf States Utilities (GSU) shut'down River Bend Station in order to perform maintenance. GSU estimates the length of the shutdown will be two to three weeks. The principal reason for the shutdown, is continued in-leakage through the condenser from river cooling water. The shutdown was accomplished as a test. The test consisted of simultaneously shutting all main steam isolation valves with the reactor at 70% rated power. All systems appeared to function normally during this reactor trip.

After this outage the River Bend licensee expects to complete its start-up test program for the station.

On March 21, 1986, GSU discovered plastic clip's dep'osited in the condenser water box. These clips (1/2" x 1/4 x 3 ) are used to hold the diffuser screens in the cooling towers. Water from the cooling towers is also used in the service water system, which contains safety related heat exchangers. Monitoring the licensee actions to assure

that safety-related coolers are not affected by these plastic clips.

I Comanche Peak Unit 1 In a Memorandum and Order dated March 13, 1986, the Commission directed establishment of a Board, by the Atomic Safety and Licensing Board Panel, to consider requests for hearing and petitions to intervene in regard to Texas Utilities Electric Company's application for extension of its construction permit for the Comanche Peak Steam Electric Station, Unit 1.

l l On March 20, 1986 the Atomic Safety and Licensing Board Panel l established the Beard, comprised of the same judges currently involved in the operating license proceeding. The scope of any proceedings will address challenges to Texas Utilities Electric Company's effort to show good cause for the extension. On March 25, 1986, an Order was issued setting a prehearing conference date on the construction permit extension issue for April 22, 1986.

'lM C 31986 ENCLOSURE B

Issuance of Possession-Only License for the Catholic University of '

America Research Reactor On March 5, 1986, the Office of Nuclear Reactor Regulation issued Amendment No. 9 to Facility Operating License No. R-13 for the AGN-201 (Serial No. 101) research reactor at the Catholic University of America, in Washington, D.C. The amendment authorizes possession, but not operation, of the reactor and its fuel while plans for decommissioning are being made by the licensee. The license will expire ten years after the date of issuance if decommissioning has not yet been accomplished.

Davis-Besse-Reactor Collant Pump Ultrasonic examination of the Byron Jackson reactor coolant pump shafts at Davis-Besse, prompted by the experience of Florida Power Corporation at Crystal River Unit 3, has revealed three of the four shafts likely to have cracks. One shaft is believed to have a 1 inch deep circumferential crack and a second shaft is believed to have a similar crack. A third shaft may have a crack and the fourth is believed not to be cracked. UT examination was done by the same team that examined the Crystal River shafts (and found all shafts cracked).

Toledo Edison Company is removing one of the cracked shafts and will send it to a hot cell for examination. Removal will require about one week. That shaft will be replaced with a spare shaft on hand so that planned system testing can continue. An order has been placed for replacement shafts. Restart of the unit is now projected for October 15, 1986 based upon shaft procurement lead time.

Palo Verde Unit 2 The resident inspector informed the staff that Palo Verde Unit 2 achieved initial entry into Mode 3 on the evening of March 25, 1986.

The last schedule provided by the utility projected the following milestones:

Initial Mode 3 entry -

3/22/86 Initial Criticality -

4/10/86 l

Ascension Above 5% power - 4/18/86 ENCLOSURE B r,m f., C 15S5

Millstone 3 -

On Monday, March 24 the licensee began power ascension from 50% to the 75% plateau. Following unacceptable SG 1evel oscillation at about 58%

power, the licensee reduced power to 50% to investigate the cause.

After adjustments were made to feed pump speed control, feed reg valve control and flow error, power was increased to 75% on Wednesday.

Although the root cause of the excessive level oscillation has not been established it has not reoccurred. The licensee is considering 2 causes:

1) feed reg valve size inconsistent with P program
2) resonance between SG 1evel and flow instrumentation (located off sam tap in Model F)

Other concerns for which the licensee is considering corrective actions are:

1) reactor coolant pump seal leakage in 2 seals
2) containment airlock inner door failure to close
3) continuation of SG sulfate concentration above 20 ppb At this time the licensee anticipates performing MSIV,10% load swing, loss of power and load rejection tests next Monday followed by cold shutdown to repair containment airlock.

Braidwood Station, Units 1 and 2 On the night of March 25, 1986, during the later phases of warming up the Main Steam lines using the MSIV Bypass Valves, the Second Stage Reheat Drain Tank hand hold gasket ruptured (two nuts were later found to be missing from the hand hole flange). This tank was inadvertently pressurized through valves that were positioned closed but were leadking.

At the time, Main Steam Header pressure was approximately 1000 psig.

! Four Reactor Coolant pumps (RCPs) had been running all day to provide heat for this evolution.

l After the four MSIV Bypass Valves had been closed; MS header pressure l dropped to about 800 psig. To expedite the MS header depressurization, I the steam dumps were used. The resultant steam flow and depressurization apparently caused a pocket of water resting on the downsteam side of the 'B' MSIV to boil and accelerate down the 200 feet of steam tunnel piping. This resulted in a water hammer which fractured l two pipe hangers at the pipe elbow at the end of this 200 foot run.

The operators initiated steam generator blowdown to control RCS temperature and prevent a S/G PORV from lifting. Within the hour, plant conditions were stabilized at 557 F and 2235 psig.

ENCLOSURE B CA.t L C 1986

Browns Ferry, Units 1, 2, & 3 ,

By phone call on March 26, 1986, Mr. Richard Gridley, TVA licensing manager, requested that the meeting which was scheduled for April 1, 1986 to discuss Browns Ferry startup issues be postponed until May 6, 1986. A meeting will be held on April 1, 1986 at which the staff will preview organization plans for the Browns Ferry plant and review the status of plant modifications for items such as fire protection, environmental qualification, etc.

McGuire 1&2 On March 26, 1986, the NRC staff and its consultant, Sandia National Laboratories, met with the ACRS Subcommittee on ECCS, Duke Power Company and Westinghouse to review Duke's request to operate McGuire 1&2 at 100% power without the Upper Head Injection (UHI) System. The Subcommittee primarily focused upon what, if any, benefit is associated with UHI as reflected by TRAC analyses with and without UHI by Sandia.

The comments at the end of the meeting appear to favc.e removal of the system in view of its operational and radiological ex?osure difficulties, its potential for SBLOCA or interfacing LOCA, its nitrogen gas in a "real-world" LOCA.

jectionSome potential, and /its members marginalfelt consultants (if that any)restrictions benefits to on peaking factor (FQ) or avoidance of irreversible removal aspects should be considered.

NRR will address the issue with the Full Committee April 10, 1986.

l ENCLOSURE B l

1,;.R L C 1986 l

O NRC TMI-2 CLEANUP PROJECT DIRECTORATE WEEKLY STATUS REPORT WEEK ENDING MARCH 28, 1986

1. DEFUELING

- As of March 30, 1986, 34 debris canisters have been transferred from the reactor vessel to pre-shipment storage with a total net weight of 38,930 lbs.

- The program for resolution of the biologic growth in the Reactor Coolant System (RCS) continues. Since the beginning of testing, 10 biocides have been examined and discounted. Of the nine biocides under active consideration, only methanol and hydrogen peroxide are relatively non-toxic. The other seven include such toxic chemicals as sodium cyanide and sodium azide. The physical methods tested indicate the organisms are relatively immune to ultraviolet light sterilization. Heating to nearly 180*F has also proven to be unsuccessful, although some kill is seen. Testing of elevated pressures shows some promise. Pressure induced by high-pressure pumps (one at 50,000 psig and one at 15,000 psig) with low volumes has been demonstrated. Further testing is in progress. A large volume (10,000 gallons) medium pressure (600 psig) system using the core flood tanks is also under study.

- The Temporary Reactor Vessel Filtration System, a swimming pool type (diatomaceous earth) filter, continues to be used for RCS filtering.

Additional swimming pool filter capacity, pending resolution of the biologic growth problem, is being planned. Approximately 50,000 gallons of RCS processed thru the swimming pool filter system yields 6 curies of Sr-90 and less than I curie each of Cs-137 and Sb-125.

2. REACTOR BUILDING ACTIVITIES

- The examinations of the upper head spaces in the steam generators show some material about 3/4 inch in size in the head space of the A generator and materials about i to i inch in size scattered about the head space of the B generator. Fiber optic viewing in the

, bottom of the A generator shows filament growth similar to that in i the reactor vessel.

3. PLANT STATUS

- The reactor remains in long term cold shutdown, vented to

! atmosphere. Core cooling is by natural heat loss to ambient l building atmosphere. The average of the incore thermocouple j readings is 81 F. The reactor coolant temperature is 73*F.

MAR 2 r 1986 ENCLOSURE B i

.. - The airborne radioactivity on the defueling platform is about 7.1 E-7 uCf/cc Tritium and 5.5 E-11 uCi/cc particulates, predominately Cesium-137. The platform is mounted above the modified internals indexing fixture which is mounted on the reactor vessel flange.

These provide water coverage of 151 feet over the core region. This water level is about 5 feet over the top of any debris canisters in the reactor vessel.

4. WASTE MANAGEMENT

- The Submerged Demineralizer System (SDS) continued processing batch 130 from the "C" Reactor Coolant Bleed Tank (RCBT) to the monitor tanks then to the "A" RCBT. SDS total processed to date is 3,885,859 gallons.

- EPICOR II was in temporary shutdown this week. EPICOR II total processed to date is 2,854,371.

5. ENVIRONMENTAL MONITORING

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

- TMI water samples taken by EPA at the plant discharge (includes

'TMI-1 and TMI-2) to the river consisted of seven daily composite samples taken from March 1 through March 8, 1986. A gamma scan detected no reactor related activity.

- The Lancaster water sample taken at the water works intake and analyzed by EPA consisted of a seven day composited sample taken from March 9 through March 15, 1986. A gamma scan detected no reactor related radioactivity.

- The NRC outdoor airborne particulate sampler at the TMI site collected a sample between March 20, and 26, 1986. No reactor related radioactivity was detected. Analysis showed Iodine-131 and Cesium-137 concentrations to be less than the lower limits of detectability.

6. AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES i

j - Installation of the balance of Defueling Water Cleanup System (DWCS) l continued.

- Kelly vacuuming continues on the contaminated areas of the 281' elevation.

Scabbling of the floor in the Neutralizer Tank Room was done this i week.

7. NRC EVALUATIONS IN PROGRESS i

( - Technical Specification Change Request number 49, and 51.

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

- SDS Technical Evaluation and System Description Update.

f,',AR 2 G 1986 ENCLOSURE B l

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. - Core Stratification Safety Evaluation. -

- Solid Waste Facility Technical Evaluation Report.

- Reactor Building Sump Criticality Safety Evaluation Report.

TMI-2 Temporary Reactor Vessel Filtration System Safety Evaluation Report, Revision 1.

- Underhead High Pressure Decon Safety Evaluation Report.

- Hydraulic Shredder Safety Evaluation Report.

- Canister Handling and Preparation for Shipment Safety Evaluation Report.

- Defueling Canister Technical Evaluation Report, Revision 2.

8. PUBLIC MEETING The Citizen's Advisory Panelson the Decontamination of THI-2 will meet April 10, 1986 at the Holiday Inn, 23 South Second Street, Harrisburg, PA from 7:00 p.m. to 10:00 p.m. At the meeting, the Panel will receive a report on the progress of defueling from GPUN. The Panel will also receive a report by the NRC staff on the status of recent TMI-2 enforcement actions. The NRC staff will also inform the Panel of ACRS (Advisory Committee on Reactor Safeguards) findings on the potential for TMI-2 recriticality during defueling.

Persons desiring to speak before the Advisory Panel are requested to contact Mr. Thomas Smithgall at 717-291-1042, or write him at 2122 Marietta Avenue, Lancaster, PA 17603.

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l ENCLOSURE B l l'AR 5' USS l

OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS ,

Items of Interest Week Ending March 28, 1986 Federally Funded Research and Development Center (FFRDC)

On March 11 and 12, 1986, NRC published a " Notice of Intent" in the Federal Register and Commerce Business Daily announcing that NRC is considering the establishment of an FFRDC for waste management technical assistance and research. An FFRDC is being considered by NRC as a potential solution to the problems of conflict of interest and long-term continuity with respect to contractual work related to the Nuclear Waste Policy Act of 1982. The Notice of Intent announced the availability of a draft solicitation package and requested public comments. Comments will be analyzed and made available to the Commission before it votes on issuance of a formal, competitive solicitation for proposals.

Sandia National Laboratories Preparing Film on Transport Package Certification In the fall of 1985, DOE's Office of Civilian Radioactive Waste Management (OCRWM) awarded a contract to the Transportation Technology Center (TTC) at Sandia Laboratories to prepare a 15 to 20 minute film on how casks (Type B package) are designed and certified. Apparently, OCRWM has contracted the preparation of several short films on various aspects of the waste program to be used at its public meetings and workshops. The " cask" film is to cover:

the process of cask design; the explanation of the design criteria to be met; and the submittal of the Safety Analysis Report to NRC. The script for the film has been written by TTC's film division. TTC recently contacted FC for assistance in making the film.

NRC Staff Review of DOE's Transportation Institutional Plan FC has coordinated review and preparation of comments on DOE's Transportation Institutional Plan, which are being forwarded to DOE's Office of Civilian Radioactive Waste Managment. Items from DOE's plan:

Oak Ridge Operations Office is responsible for developing options for operating the NWPA transportation system.

Chicago Operations Office will manage contracts for studying / resolving transportation institutional issues.

OCRWM and DOT are considering a jointly sponsored seminar on routing regulations and guidelines.

i ENCLOSURE C ffAR S " 1996 l

NFS-Erwin -

Strike by OCAW members continues. There has been no progress made in resolving differences between the Union and NFS. A recent proposal by the OCAW Union to return to work for a "90-day cooling-off period" was rejected by NFS. Nothing less than a one year contract will be considered by NFS. NFS continues to conduct limited operations of the HEU production and scrap recovery operations.

On March 12, 1986, a grass fire was discovered outside the protected area at the NFS facility, Erwin, TN. The blaze was apparently caused by a flare. The Erwin Volunteer Fire Department was harassed by the Union pickets and was delayed in reaching the fire. No damage was experienced by the Erwin facility due to this delay. On March 19, 1986, another grass fire occurred outside the protected area. On March 20, 1986, a building on the site, also outside the protected area, suffered fire damage. In the last two cases, the Erwin Volunteer Fire Department and local law enforcement personnel responded in a timely manner with no harassment encountered from the striking Union pickets.

All three fires are currently under investigation.

Region II has carefully reviewed the security program that NFS has in place to protect against adverse actions and has found it to be at an appropriate level.

the Division of Safeguards concurs.

Nuclear Employee Data System (NEDS)

On Tuesday, March 25, 1986, representatives of six utilities briefed Safeguards staff from Region I, Region II, NRR, IE, ELD and NHSS on the Nuclear Employee Data System (NEDS). The NEOS is a computer based system that stores information concerning transient workers being screened for unescorted access authorization. Participating utilities will use standardized screening and evaluation criteria which meet or exceed industry standards and will perform inter-utility audits to ensure that standards are being met. The system is scheduled for implementation in June 1986.

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Office of Inspection and Enforcement Items of Interest Week Ending March 28, 1986 .

1. The following Significant Enforcement Actions were taken during the past week:
a. EN 85-29A, upon careful consideration of the licensee's (Mississippi Power and Light Company, Grand Gulf) response, the staff concluded that the proposed civil penalty should be withdrawn. The original action was related to the development of technical specifications for operation.
b. EN 85-48A, an Order Imposing Civil Monetary Penalties in the amount of $2,500 was issued on March 20, 1986 to Frances Mahon Deconess Hospital (Glasgow, MT). This action was based on several health physics violations, one of which included the use of licensed material by an unauthorized user.
c. EN-86-14, a Notice of Violation and Proposed Imposition of Civil Penalty was issued March 24, 1986 to Abington Memorial Hospital (Abington, PA) in the amount of $2500. This action is based on numerous violations of NRC requirements regarding safe health physics practices.
d. EN 86-15, a Notice of Violation and Proposed Imposition of Civil Penalty was issued to Ambric Testing and Engineering Associates of Virginia, Inc. (Alexandria, VA) on March 26, 1986 in the amount of

$250. This action was based on multiple violations of health physics practices and control of licensed material,

e. EN 86-16, a Notice of Violation and Proposed Imposition of Civil Penalty was issued to American Electric Power Services Corporation, Indiana Michigan Electric Company (D.C. Cook) on March 26, 1986 in the amount of $100,000. This action was based on multiple violations of surveillance testing and procedure development with regard to containment leak rate testing.

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

l l a. PNS-I-86-04, GPU Nuclear Corporation (0yster Creek), Bomb Threat.

f b. PNO-I-86-22, GPU Nuclear Corporation (0yster Creek), Small Unmoni-tored Release.

I c. PNO-I-86-23, Pennsylvania Power & Light Company (Susquehanna Unit 1)

Unusual Event - workman injured / contaminated. -

ENCLOSURE D u n r,P E 3 l

2

d. PNO-II-86-228, Nuclear Fuel Services, Inc. (Erwin, TN), Third Fire on Plant Property,
e. PNO-II-86-23, Virginia Electric & Power Copmpany (North Anna Unit 1)

ESF Actuation from 100 Percent Power.

f. PNO-III-86-26A, Ferris State College (Big Rapids, MI), Apparent TritiumOverexposure(Update).
g. PN0-III-86-29, Allied Chemical Company (Metropolitan, IL) Uranium Hexafluoride Cylinder Overfill
h. PN0-III-86-30, Comonwealth Edison Company (Braidwood Unit 1), Water Hammer Damages Pipe Supports.
3. The following IE Information Notices and IE Bulletins were issued during the past week:
a. IE Information Notice No. 86-17, Update of Failure of Automatic Sprinkler System Valves to Operate was issued March 24, 1986 to all nuclear power reactor facilities holding an operating license or a construction permit.
b. IE Information Notice No. 86-18, NRC On-Scene Response During a Major Emergency was issued on March 26, 1986 to all nuclear power reactor facilities holding an operating license or a construction permit.
c. IE Information Notice No. 86-19, Reactor Coolant Pump Shaft Failure at Crystal River, was issued on March 21, 1986 to all nuclear power

. reactor facilities holding an operating license or a construction permit.

4. Other Items
a. Senior Management Meetings (1) Director, IE and Director, Division of Inspection Programs, participated in the exit meeting of the TMI-1 Safety System Functional Inspection this week.

(2) Director, IE participated at the SMUD briefing on planned recovery for Rancho Seco this week.

b. Civil Penalties Paid (1) Nebraska Public Power District (Cooper) in the amount of

$50,000 for violations involving the control of surveillance testing (EA 86-03).

(2) Duke Power Company (0conee) in the amount of $25,000 for

,2 00 286 vi lations involving access control (EA 86-21).

ENCLOSURE D

3 (3) Boston Edison Company (Pilgrim) in the amount of $25,D00 for violations involving weakness in a vital area barrier (EA 85-106),

c. Incident Response On March 25, 1986, members of the Incident Response Branch, Division of Emergency Preparedness and Engineering Response, participated in an exercise in a limited manner with Region III and LaSal'e Nuclear Power Plant.
d. Vendor Program Members of the Vendor Programs Branch, Division of Quality Assurance, Vendor, and Technical Training Center Programs participated in the following inspections this week:

(1) Review manufacturing records and gather data on design changes, recommended maintenance programs and the vendor /

> licensee inerface regarding swing-type check valves.

(2) Chem Nuclear Systems, Inc. (Columbia, SC) to review maintenance work, maintenance / repair procedures, and QA program and practices to determine compliance with 10 CFR 71 for transpor-tation packages.

(3) Philadelphia Electric Company (Peach Bottom and Limerick) to obtain information on swing check valves and flexible conduit and to inspect RPS transfer panels.

(4) GPU Nuclear Corporation (0yster Creek) to review equipment qualification program implementation to determine conformance to requirements of 10 CFR 50.49.

(5) Public Service Company of Colorado (Ft. St. Vrain) to prepare for the equipment qualification inspection,

e. Enforcement Conference The Branch Chief, Safeguards & Materials Programs Branch, Division of Inspection programs, participated in an enforcement conference in Region III with Allied Chemical Company on March 20, 1986.
f. Technical Training Center The first courses on the TTC BWR control room simulator were con-ducted last and this week.

l ENCLOSURE D EAR 2 C '986

4

g. Maintenance Program Reviews Members of the Operating Reactors Program Branch, Division of Inspection, participated in the review of the Toledo Edison Company (Davis-Besse) maintenance program this week.
h. Quality Assurance A member of the Quality Assurance Branch, Division of Quality Assurance, Vendor, and Technical Training Center programs, was in Region II for the presentation by Georgia Power Company on several readiness review modules this week,
i. Emergency Preparedness (1) A republication copy of NUREG/CR-3365, " Guidance for Preparing Scenarios for Emergency Preparedness Exercises at Nuclear Generating Stations (Draft Report for Coment)," was provided to the regions. The document will receive wide distribution and a Notice of Availability will be published in the Federal Register.

(2) An emergency preparedness exercise report provided by FEMA for Maine Yankee was forwarded by IE to Region I for appropriate action. One deficiency regarding route alerting has been satisfactorily resolved.

(3) Emergency preparedness exercise reports for Gina, Palisades, and Quad Cities were forwarded by IE to the regions for appropriate action. No deficiencies were identified that would result in a negative finding concerning offsite emergency preparedness for the sites evaluated.

(4) FEMA has reported (in accordance with their rule 44 CFR 350) that the public alerting and notification system for D.C.

, Cook meets the current FEMA and NRC criteria and is acceptable.

The' state anc county emergency preparedness plans for D.C. Cook were previously approved.

3 ;; $6 ENCLOSURE D

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t OFFICE OF NUCLEAR REGULATORY RESEARCH Items of Interest -

I Week Ending March 28, 1986 SOURCE TERM BRIEFING 4

l A quarterly briefing on source tems was presented to the Comission on March 26, 1986. David Torgerson of the Atomic Energy of Canada, LTD. presented 4

a sumary of the recently published OECD report, Nuclear Reactor Accident Source Terms. This report surveys the source term studies of a number of U.S.

and foreign groups to identify (a) areas where information appears to be suffi-cient, (b) areas where the studies disagree, (c) generic issues that could be applied to most LWRs, and (d) barriers to applying source term information to different LWRs. The final recommendation of that presentation was that

. uncertainties should not delay implementation of new source term information, ,

and that research needed to reduce uncertainties should be part of an itera-  !

I tive process with the applications.

I '

R. O. Meyer, RES, described the status of the final version of NUREG-0956,

" Reassessment of the Technical Bases for Estimating Source Terms," which is now j scheduled for publication in July 1986. T. P. Speis, NRR, and Z. R. Rosztoczy, NRR, discussed the severe accident implementation program and source-term-

. related regulatory changes; no major decisions will be made in these efforts until after NUREG-0956 is published in final form. M. L. Ernst, RES, discussed the status of the risk rebaselining work, which utilizes the source tem technology described in NUREG-0956; the risk rebaselining work will be pre-sented in Draft NUREG-1150, which will be issued for comment in September 1986.

All three of the above NRC efforts were recently described in the " Status Report on Severe Accident Source Ters Reassessment," SECY-86-96, March 24, 1986. Additional information on the " Implementation Plan for the Severe Accident Policy Statement and the Regulatory Use of New Source-Term Infoma-i tion" was given in SECY-86-76. February 28, 1986.

f Nuclear Plant Analyzer Program (NPA)

! The NPA provides interactive control of NRC's thermal hydraulic analysis

codes with a variety of user-friendly features and colorgraphics output.

Idaho National Engineering Laboratory recently completed coarsely-modalized, ,

fast-running input decks for the Oconee and H.B. Robinson plants. These input decks will be used by NRC staff or contractor personnel to perform system transient analyses.

i ENCLOSUR E E IJT.9 2 ' T,3

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Visit by Dr. Klaus Becker, West Germany Dr. Klaus Becker, Head of the nuclear section of the Gernen Standards Institute (DIN), visited NRC on March 25, 1986, to meet with RES management.

Dr. Becker's visit to the U.S. was prompted by a proposed German fuel reprocessing plant in Bavaria. He was especially interested in NRC's radiation protection standards (proposed revision of 10 CFR Part 20), the impact of increasing the quality factor for neutrons recommended by the International Commission on Radiological Protection (ICRP) and personnel dosimetry and recordkeeping as it related to compensation claims for possible radiation induced cancers. Dr. Becker is also visiting other Federal Agencies and organizations having interest in these matters.

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l ENCLOSURE E t,,,r,:_ ,u ..ua L

Recently Issued Publications Draft Regulatory Guide and Value/ Impact Statement: Station Blackout Task SI 501-4. Comments requested by June 19, 1986.

Contact:

A. M. Rubin (301) 492-8303 Notice of Change in Availability of Final Regulatory Guides The following information will be published in the Federal Register shortly.

Final regulatory guides published by the Nuclear Regulatory Commission (NRC) after public comment are no longer available on a subscription basis from the Superintendent of Documents, U. S. Government Printing Office (GPO).

Copies of final regulatory guides will continue to be ' sold by GP0 as individual publications. Information on availability and pricing may be obtained by contacting the U.S. Government Printing Office, P. O. Box 37082, Washington, DC 20013-7082, Telephone: (202) 275-2060 and (202) 275-2171.

i NRC has made arrangements with the National Technical Information Service (NTIS-)

to provide a standing order service for regulatory guides. Anyone having a deposit account with NTIS may place standing orders through the NTIS Subscription Department for final regulatory guides in specified divisions as they are issued.

Customer accounts will be billed ,$5.50 for each regulatory guide mailed by NTIS.

For details on establishing an NTIS deposit account or for placing a standing order for regulatory guides, write to NTIS, 5285 Port Royal Road, Springfield,

' VA 22161.

Draft regulatory guides will continue to be available on request to the NRC.

All current subscribers have been placed on NRC's mailing list to receive draft regulatory guides as they are published and, in addition, to receive notices of availability when new final regulatory guides are published.

Any inquiries concerning the availability of NRC's regulatory guides may be directed to Publication Services (P-110), U. S. Nuclear Regulatory Commission.

l Washington, DC 20555, Telephone: (301) 492-7914.

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ENCLOSURE E l V.;;; u, u, ,Sc_,o i

t i e- ea.

RES RULEMAKING ACTIVITIES Emergency Preparedness for Fuel Cycle and Other Radioactive Materials Licensees (Parts 30, 40, 70)

In 1981 the NRC issued orders to certain fuel cycle and other radioactive material licensees requiring them to submit comprehensive onsite radiological emergency plans. Rulemaking was initiated on August 3,1981, for codification of those orders.

The Acting E00 signed the rulemaking package on March 25, 1986, and forwarded it to the Commission.

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 used to support NRR's review of IDCOR submittals. In addition, it will support the staff report NUREG-1150, which is intended to provide guidance to decision-makers as to the appropriate role of infonnation on core melt frequency, containment performance, source terms, and risk in making severe accident decisions.

The Comission was briefed on March 26, 1986, with regard to the status of NUREG-1150 and NRR's implementation program. At that briefing the Comission was advised of a slip in publication of the draft NUREG-1150 from mid-August to September 30, 1986. The reasons for the slip are the sheer bulk of the analyses and documentation; the need for a high quality product, which has resulted in a very substantive peer review process; and slips in NUREG-0956, upon which NUREG-1150 must rely. There is a full-day ACRS subcomittee meeting scheduled in Albuquerque, New Mexico, on May 1, 1986.

Risk Effectiveness of LWR Regulatory Requirements The purpose of this program is to identify existing regulatory requirements that have marginal importance to safety, and to make recomendations to the E00 whether to eliminate or modify these requirements.

A copy of the contractor's Task 1 final report, entitled " Review of Light Water Reactor Regulatory Requirements: Identification of Regulatory Requirements That May Have Marginal Importance to Risk," NUREG/CR-4330, Volume 1, was received on March 24, 1986. A revised draft of the Task 2 report, evaluating risk effectiveness of three separate areas: containment leakage; leakage control system for main steam isolation valves; and regulatory review of nuclear fuel design, was distributed to staff for review and coment. Staff coments on the Task 2 report are expected to be forwarded to the contractor by early April 1986. Representatives of various NRC offices met on March 20, 1986, to discuss preliminary staff positions concerning potential modification of containment leakage requirements. Representatives from Regions II and III were unable to attend the meeting but they provided their coments individually. Coments expressed at the meeting will be incorporated into the revised draft.

ENCLOSURE E

? 0 : 1986

ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS .

WEEK ENDING l%RCH 28, 1986 U.S.-Indonesian Joint Steering Comittee On March 18 the first U.S.-Indonesian .?oint Steering Comittee was held at the State Department with U.S. representatives from State, DOE, NRC, ACDA, and Connerce participating. Topics for the meeting included:

status of nuclear energy programs in both the U.S. and Indonesia, past U.S.-Indonesian cooperation, and areas for future cooperation in nuclear energy. IP represented NRC at this meeting.

On March 19 the Indonesian delegation paid a visit to Jack Roe, DEDO, to learn more about NRC's responsibilities in both the domestic and international areas and to tour the NRC Operations Center.

, Indonesia-U.S. Joint Seminar on Nuclear Technology, April 8-10_, 1986 Jack Roe, DEDO, will represent NRC at the Indonesia-U.S. Joint Seminar on Nuclear Technology April 8-10, 1986, in Jakarta, Indonesia which is being organized by the Interagency Task Force on Nuclear Exports. This is the fourth time NRC has participated in this type of seminar. The three previous seminars were held ir. Mexico, Yugoslavia, and Portugal.

International Vacancy Notices The following vacancy notices from the International Atomic Energy Agency located in Vienna, Austria have been posted on NRC bulletin boards:

l P-3 Soil Microbiologist, Soils Unit, Agriculture Laboratory, Seibersdorf Laboratory, Division of Research and Laboratories, Department of Research and Isotopes

P-5 Senior Safeguards Analyst, Section for System Studies, Division j of Development and Technical Support, Department of Safeguards P-5 Transport Safety Specialist, Radiation Protection Section, Division of fluclear Safety, Department of Nuclear Energy and Safety i P-4 Non-Destructive Analysis (NDA) Specialist, Section for Data l Evaluation, Division of Safeguards Evaluation, Department of Safeguards l P-4 Thesaurus Specialist, INIS Section, Division of Scientific and Technical Information, Department of Nuclear Energy and Safety ENCLOSURE G l MA2 0 01986

2 International Vacancy Notices continued P-3 Isotope Hydrologist, Isotope Hydrology Section, Division of Research and Laboratories, Department of Research and Isotopes Foreign Visitors On March 19 and 21 Dr. Michael Herttrich Der Bundesminister des Innern of the Federal Republic of Germany, visited NRC for discussions with NRR and RES on a range of topics, including PWR containment systems analysis, use of PRAs for BWRs, status and implementation of probabilistic safety goals, accident management and severe accident source term reassessment status and regulatory implications.

On March 28 Mr. Ernst Welteke, majority leader of the Hessian State Parliament in the FRG, visited NMSS to obtain a general overview of U.S.

programs in nuclear waste management and NRC's role in this area.

t ENCLOSURE G IRP,001986

OFFICE OF STATE PROGRAMS ITEMS OF INTEREST -

WEEK ENDING MARCH 28, 1986 New Mexico Request to Turn Back Uranium Mill Tailings Regulation to NRC NRC has received a letter dated March 18, 1986 from the Governor of New Mexico requesting that the NRC reassert its authority over uranium mills and uranium mill tailings. The State has requested an effective date of May 1, 1986.

State Program Review The Utah radiation control program will be reviewed by Region IV the week of April 7, 1986.

North Carolina's Denial of US Ecology's Incinerator Application OSP was informed by the Director of the North Carolina Radiation Control Program that North Carolina denied US Ecology's license application for a commercial incinerator by letter dated March 21, 1986. The State cited US Ecology's past performances and lack of sufficiently qualified personnel to operate the incinerator as the basis for the denial. On February 13, 1986, the Director of the Division of Environmental Management, the agency responsible for issuing air quality permits, denied US Ecology's application for such a permit for similar reasons.

ENCLOSURE H una 2 L 1986

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b ITEMS ADDRESSED BY THE COMMISSION - WEEK ENDING MARCH 28,'1986 A. STAFF REQUIREMENTS - PERIODIC BRIEFING BY~ REGIONAL ADMINISTRATORS, 10:00 A.M.

WEDNESDAY, MARCH 19, 1986, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPDi TO PUBLIC AIItNDANCE) Memo SECY to V. Stello and H. Plaine dated 3/26/86 The Commission was briefed by the staff and regional adminis-trators from Regions I and V.

Chairman Palladino, noting that the staff has recently proposed major revisions to plant technical specifications (tech specs),

asked the' staff to advise him as to how the tech spec changes

, would impact on activities of all of the regions.

l Commissioner Each reduested I information from the staff on the threshold used by the regions to determine when to send an augmented team to a plant to investigate an event or plant performance. He also requested the regional administrators to provide him the performance indicators they use to monitor a plant's performance.

(The EDO promised responses to the above requirements at the

Commission meeting with regional administrators from Regions II,.III, and IV, scheduled for Wednesday, March 26, 1986.)

, Commissioner Bernthal requested that the staff and OGC study i and report back to the Commission on the conflict of interest aspects of employment by state public utility commissions of i former NRC employees whose duties with NRC regional offices included regulation of plants located in the employing PUC's state.

(ELD /OGC) (SECY Suspense 4/4/86) i i Commissioner Asselstine suggested that the staff should compare i the results of regional team inspection findings to those of i INPO for plants inspected.

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i ENCLOSURE O

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. B. STAFF REQUIREMENTS - AFFIRMATION / DISCUSSION AND VOTE, 4:30 A.M., THURSDAY, MARCH 20, 1986, COPHISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to V. Stello, H. Plaine, C. Kammerer and J. Fouchard dated 3/27/86 I. SECY-86 Final Rule to Modify General Design Criterion 4 of Appendix A, 10 CFR 50 The Commission, by a 5-0 vote, approved a final rule which modifies General Design Criterion 4 of Appendix A to 10 CFR Part 50 to allow the exclusion of certain dynamic effects associated with postulated pipe ruptures in the primary coolant loop piping i of pressurized water reactors.

The Federal Register Notice should be forwarded for signature and publication in the Federal Register and the appropriate Congressional and public announcements should be made.

(EDO/OCA/OPA) (SECY Suspense: 4/18/86)  !

II. SECY-86 Review of ALAB-819 (In the Matter of Philadelphia Electric Company) i The Commission, with Chairman Palladino and Commissioners Roberts, Bernthal, and Zech. agreeing, approved an order denying requests by the Philadelphia Electric Company, the Limerick Ecology Action, and Robert Anthony / Friends of the Earth, seeking Commission review of various aspects of ALAB-819. Commissioner

~Asselstine approved in part and disapproved in part and provided separate comments.

(Subsequently, on March 20, 1986 the. Secretary signed the Order.) '

l III. SECY-86 Review of ALAB-823 (In the Matter of Philadelphia Electric Company)

The Commission, by a 5-0 vote, approved the issuance of an order denying the motion filed by Robert Anthony / Friends of the Earth I to reopen the record and stay operation of Limerick Generating Station, Unit 1. ,

(Subsequently, on March 20, 1986 the Secretary signed the Order.)

p, r.1986 ENCLOSURE O

3-B. CONTINUED IV. SECY-86 Response to Commission Questions on Braidwood The Commission, by a 3-2 vote, approved an order denying review of ALAB-817 and requesting parties to submit briefs on the issue of whether the five-factor test for submission of a late filed contention is satisfied by the intervenors amended quality assurance contentions.

Chairman Palladino and Commissioner Asselstine disapproved and provided separate views.

(Subsequently, on March 20, 1986 the Secretary signed the Order.)

V. SECY-86 TMIA Motion to Dismiss and for Stay of Husted Hearing The Commission, by a 5-0 vote, approved an order denying a motion from TMIA that requested the Commission dismiss the order granting Charles Husted a hearing and stay the proceedings.

(Subsequently, on March 20, 1986 the Secretary signed the order.)

C. STAFF REQUIREMENTS - STATUS BRIEFING ON FERMI, 2:00 P.M., WEDNESDAY, MARCH 12, 1986, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (PORTION OPEN TO PUBLIC X'TTENDANCE) Memo SECY to V. STello dated 3/28/86 The Commission met with the staff to discuss the status of staff activities with respect to Detroit Edison's Enrico Fermi Atomic Power Plant, Unit 2 (Fermi-2).

In addition to the staff the following persons made presenta-tions to the Commissions

(

l Jennifer Puntenney Michigan Safe Energy Coalition Sister Barbara Bacci Sisters, Servants of the Immaculate Heart of Mary Walter McCarthy Chief Executive Officer Detroit Edison Company ENCLOSURE 0 In.'t 2 L 1995 l

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C. CONTINUED The Commission requested that the licensee include the chairman of their " Overview Committee" in a future commission briefing that will precede restart of Fermi-2.

Chairman Palladino requested the staff to provide information ,

, to the Commission as to whether the Fermi-2 emergency prepared-ness exercise was litigated.

(ELD) (SECY Suspense: 4/21/86)

Commissioner Each recommended that the licensee ask INPO to l evaluate Fermi-2 prior to reactor restart.

D. STAFF REQUIREMENTS - BRIEFING BY SOUTHERN CALIFORNIA EDISON CO. ON SAN ONOFRE-1, 10:00 A.M., TUESDAY, MARCH 18, 1986, COMMISSIONERS' CONFERENCE ROOM, D.C.

OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to V. Stello dated 3/28/86 The ccamission met with representatives of. Southern California Edison (SCE) Co. to discuss the November 21, 1985 loss of power / water hammer event at San Onofre Unit 1.

I The following persons participated in this meeting:

David J. Fogarty Executive Vice President, SCE Kenneth P. Baskin Vice President Nuclear Engineering Safety and Licensing, SCE Mark O. Medford, Manager Nuclear Licensing, SCE

, Russ W. Krieger, Manager Operations, SCE

Dr. Lawrence Papay Senior Vice President, SCE l

l Jack Rainsberry, Supervisor

! San Onofre Unit 1 Licensing Commissioner Zech requested staff to advise licensees of the potential generic implications of the age-related cable failure

at San Onofre-1.

(NRR) (SECY Suspense 4/30/86) l ENCLOSURE O l UAR 2 C 1966 em -c., r-_._m m-- ,.-, y- - ,_. , , , . . _ _ . . , ,

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D. CONTINUED commissioner tech also requested staff to discuss with INPO and others the generic question of using plant electrical blueprints in operator training to enable operators to pinpoint electrical problems.

(NRR) (SECY Suspense: 5/30/86),

Chairman Palladino requested staff to provide information on the design basis for containment energy mitigation in San Onofre-1 and whether the staff is satisfied with the arrangement.

(NRR) (SECY Suspense 4/30/86) l l

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I?AR 2 e 1ggg ENCLOSURE 0

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[( NRR MEETING NOTICES *

  • e, MARCH 28, 1986-I$

o>

DOCKET APPLICANT /

DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 3/31/86 50-155 Room P-114 Discuss 10 CFR 50, Appendix R Consumers J. Zwolinski 1:00 p.m. 50-255 Phillips Bldg. issues for the Big Rock Point Power Co.

and Palisades Plants.

4/1/86 50-213 Room 6110 Discuss the licensee's request NU F. Akstulewicz 10:00 a.m. MNBB for schedular exemptions from the fire protection requirements of Appendix R.

4/1/86 50-259/ Browns Ferry Discuss organizational plans and TVA M. Grotenhuis 8:00 a.m. 260/296 Plant Site review status of plant modifications.

4/8/86 50-315 D.C. Cook Discuss the site organization IMEC D. Wigginton 8:00 a.m. 50-316 Site and plant management issues in Stevensville, regards to meeting regulatory Michigan requirements and technical-specifications.

4/8/86 -

B&W Owners Discuss the draft plan being B&W Owners W. Paulson 9:30 a.m. Group developed by the B&W Owners Group Group to address the NRC staff's concerns relative to the frequency of reactor trips and the complexity gg of post-trip responses in B&W F2 designed plants. '

8 e

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

Si x

  • cs c3 NRR MEETING NOTICES
  • G ER MARCH 28, 1986 DOCKET APPLICANT /

DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 4/10/86 50-412 Room P-110 Discuss with DLC its progress DLC P. Tam I

10:00 a.m. Phillips Bldg. in the WHIPJET Program (Use of ,

leak-before-break assumption for '

balance-of-plant piping). This is the third progress report meeting.

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5: ,

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

NMSS MEETING NOTICES

!! FOR WEEK ENDING: 3/28/86 ll Division of Fuel Cycle and Material Safety

$$ DOCKET ATTENDEES /

ll DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT 3/28-4/2/86 San Diego, To meet with Region V inspector at N. Ketzlach (FC) Ketzlach CA licensee facility (General Atomic) RV Rep.

to review operations and organization. Reps of General Atomic 4/1/86 Willste Meeting with Navy representatives to V. Miller (FC) Miller 1:00 pn 5th floor discuss the application for a Navy F. St. Mary (FC) conf room broad license. J. Hickey (FC)

R. Cunningham (FC)

J. Metzger (IE)

Navy Representatives 4/5-12/86 Vienna, Participate as U.S. expert in IAEA D. Cool-(FC) Cool Austria advisory group.

4/8-10/86 Seattle, Present a paper at the Third Inter- L. Rouse (FC) Rouse WA national Symposium on Spent fuel J. Roberts Storage Technology.

4/15/86 Docket Hartsville, Meeting and visit to discuss ISFSI J. Roberts (FC) Roberts 72-3 NC application with Carolina Power & F. Sturz (FC)

Light at H.B. Robinson site. J. Schneider (FC)

J. Counts (IE)

Reps of CP&L Division of Safeguards None e

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$ 2 i a

e . .

MilSS MEETINr. NOTICES .

nivimian of Waste Management e

B i ATTENDEES CONTACT

$ DATE LOCATION PURPOSE is Discuss NRC comments and reach JLinehan, WMRP RJohnson April 24-25 D00, Washington, DC 3 forrestal Bldg. agreement on DOE's approach to RJohnson, WMRP level of detail in the Site JKennedy, WMRP Characterization Plan SCoplan, WMRP dirapp, WMGT JBuckley, WMEG KChang, WHEG DOE sta f f ,

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, . , RES MEETING NOTICES March 28, 1986 i

ATTENDEES /

i

$ DATE/ TIME LOCATION PURPOSE APPLICANT NRC CONTACT

=

ra i

4/9/86 AR-5033 . Contractor briefing on tech spec research NRR, RES, DRobinson

BNL, SAI i

1 4/9/86 1133-SS Meeting with DOE on advanced reactors DOE DFRoss i RES

NRR l

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5' March 28, 1986

  • 2 RII MEETING NOTICE b$ DOCKET ATTENDEES /

DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT 4/2/86 RII Office Quarterly Regional Meeting Resident Inspectors, Walker-of Resident Inspectors Selected HQs and Regional Staff Members 9:30 am RII Offfice Representatives of CP&L Licensee and Selected Gibson are meeting in RII to Regional Staff Members discuss fire protection requirements at the Harris Plant 4/3-4/86 Soddy-Daisy, TN Commissioner Asselstine Commissioner Asselstine, 01shinski and members of his staff Deputy Regional Administra-are at the Sequoyah site tor for TVA, and Resident for site familiarization Inspectors 1

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