ML20043F241

Informs Commission of 900417 Meeting W/Mexican Nuclear Commission Re Nuclear Activities Per Nrc/Mexican Nuclear Commission Agreement to Exchange Technical Info & Cooperation in Nuclear Safety

ML20043F241
Person / Time
Issue date:	05/11/1990
From:	Harold Denton NRC OFFICE OF GOVERNMENTAL & PUBLIC AFFAIRS (GPA)
To:
References
TASK-PII, TASK-SE SECY-90-166, NUDOCS 9006140282
Download: ML20043F241 (46)

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i POLICY ISSUE 1

11.; 1990 (Information)

SECY-90-166 g:

The Commissioners i

M From:

Harold R. Denton, Director Office of Governmental-and Public Affairs l

Subject:

MEETING

SUMMARY

WITH THE MEXICAN NUCLEAR COMMISSION -

APRIL 17, 1990 i

Purpose:

To inform the Commission about a meeting with the Mexican Comision Nacional de Seguridad Nuclear y i

Salvaguardias (CNSNS) involving Region IV Administrator, Robert Martin, and members of GPA/IP Discussion:

On April 17, 1990, I met with Mexican nuclear officials j

in El Paso, Texas. The purpose of the meeting was to L

update and review NRC and CNSNS nuclear activities 1

pursuant to the NRC/CNSNS Agreement to Exchange Technical Information and Cooperation in Nuclear Safety. Attached is a copy of the meeting summary.

Our conversations ranged over a number of topics covering our respective programs and mutual interests in cooperation. The Mexicans showed particular interest in maintenance, performance indicators, the SALP process, root cause analysis of events, and emergency planning.

They reported on the status of Laguna Verde and steps j

they need to take to have a smooth operation.

The last high-level meeting between the two parties was held in September 1987, and' included discussions in Mexico City as well as a tour of the Laguna Verde nuclear power plant, then under construction, k

Harold R. Denton, Director 1

9006140282 900511 Office of Governmental and

.F_ R ECY Public Affairs PDC

Attachment:

As stated

Contact:

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Michael B. Congdon, GPA s

(21786)-

NOTE:

TO BE MADE PUBLICLY AVAILABLE IN 10 WORKING DAYS FROM THE DATE OF THIS PAPER.

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qay 4 1990 i

i MEMORANDUM FOR: Harold R. Denton, Director Office of Governmental and Public Affairs THRU:

Ronald D. Hauber, Director, International Programs Office of Governmental and Public Affairs

[.j FROM:

Victor Benaroya, Assistant Director N#

s International Policy and Reactor Safety Cooperation, GPA/ P Karen Henderson, Policy Analyst

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International Security, Exports, and Ma erials Safetg; GPA/:1.P L

SUBJECT:

APRIL 17, 1990 MEETING WITH OFFICIALS OF THE MEXICANTOMISION NACIONAL DE SEGURIDAD NUCLEAR Y SALVAGUARDIAS u

On April 17, 1990, a meeting was held in El Paso, Texas, with Ing. Miguel-Medina Vaillard, Director General of.the Mexican Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS), and the Heads of the CNSNS's three offices: Mr. Jose Luis Delaado Guardado, Nuclear Safety; Dr. Jose Raul Qritz Magana, Radiological Protection; and Dr. Sergio Waller Mejia, Technology, Regulation and Services.

The NRC was l

represented by Mr. Harold Denton, Director of the Office of Governmental and Public Affairs; Mr. Victor Benaroya, Assistant Director for International Policy and Reactor Safety Cooperation, GPA/IP; Mr. Robert Martin, r

l Administrator for Region IV; and Dr. Karen Henderson,-Policy Analyst, GPA/IP.

The purpose of the meeting was to update and review NRC and CNSNb nuclear activities pursuant to the NRC/CNSNS Agreement to Exchange Technical Information and Cooperation in Nuclear Safety. The last high-level meeting between the two parties was in September 1987, and included discussions in

• Mexico City as well as a tour of the Laguna Verde nuclear power plant then under construction.

The discussions in the morning provided a general. overview of NRC activities, including descriptions of available data sources 'such as the SCSS, FEF, and NPRDS and'their use; studies and evaluations relevant to the operation of BWRs; the technical specifications improvement program; SALP and recent work in the area of performance indicators; NRC emphasis on maintenance; review of u

advance plant designs; aging and license renewal; PRAs and IPEs; source term; D

emergency procedures; emergency response; training; and inspection techniques.

Also discussed were current Mexican /NRC exchanges of personnel and information and responses to the recent materials-handling incidents which have' occurred on both sides of the border. The Mexicans were especially interested in maintenance (Laguna Verde is barely keeping up with repairs), performance indicators, use of the SALP process to monitor trends at Laguna Verde, methods in performing better root cause analyses, and emergency response (the utility l

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g Harold R. Denton 2

ey 4 t990 bt had two full-scale emergency drills). During the meeting, we provided the b m :ans with the documents listed in Attachment 1.

Mr. Medina led the afternoon discussions, beginning with a brief description of the statutory history and evolving responsibilities of the CNSNS and associated nuclear research and er.ergy institutes. Of particular interest were the revisions of Mexican nucienr law in 1980 and again in 1985 which increased CNSNS's nuclear safety responsibilities (from 3 to 25 sections defining and establishing regulatory norms for nuclear safety and radiological protection) and their authority to license and impose sanctions on licensees.

In addition, Mr. Medina described the reorganization of, and chain of command for, the cognizant nuclear agencies within the Mexican government which made the CNSNS an independent ("desconcentrado") body reporting directly to the Secretariat for Mines, Energy and Parastatals. Mr. Medina briefly covered regulations which are in process in the areas of nuclear installations and radioactive materials transport; the adoption of ICRP, NUSS, and IAEA guidelines; and the Mexican reliance on NRC standards and regulations for the licensing of the country's first nuclear project. Mr. Medina also summarized the status of the Laguna Verde nuclear power plant.

Unit I reached 100 percent power for the first time on March 17.

It is scheduled to perform the 100-hour acceptance test in May, af ter which it will be declared "commerci al. " It is expected that it will take three more years to complete Unit 2.

There Dr. Ortiz gave a review of Mexico's radiological protection program.

are currently 700 licensees in Mexico, including 300 medical and 250 industrial lic%e holders. He indicated that among the CNSNS's problems (1) discovv ng and controlling "open' sources (i.e., for human are:

e administration' which are often illegally imported into the country; (2) sorting c a responsibilities for controlling the use of sources which might fall uner the overlapping purviews of the CNSNS, health, and environmental 6:thorith

• and (3) regulating industrial radioaraphy, Mr. Delgado gave an ove' slew of CNSNS's experiences in licensing the Laguna Of parti <21ar interest was his description of how the CNSNS, Verde plant.

independently of the t,ility, analyzes the root causes of events and then CNSNS and the meets with the utill's to resolve any differences in analysis.

the steps to bt taken to avoid repetition of problems.

utility also discus 3 He noted that most of Laguna Verde's operators came from thermal plant backgrounds, and that the utility has already acknowledged the differences in The Mexicans have already conducted a PRA operating the two kinds of plants.

Level 1 on Laguna Verde and plan to request an ASSET from lAEA to help with root cause ars'ysis.

Finally, Dr. 'hlbr descrii+d his office's functions in providing technical support in source term PRA, and transients, as well as translations and The documentation of rules and regulations, data processing, and training.

information provided by the Mexicans is in Attachment 2.

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3 Harold R. Denton During the discussions it was agreed that the NRC would provide the items I

We also agreed to inform the CNSNS of activities

' listed in Attachment 3.

listed in Attachment 4.

l The meeting ended on a positive note. Mr. Delgado extended an invitation to

. Chairman Carr to meet at the Laguna Verde site before the end of the year.

Attachments:

1.

List of Documents Provided by NRC During the Meeting Information Provided NRC by CNSNS 2.

List of Documents to be Provided to CNSNS by NRC 3.

4.

List of Activities that CNSNS will be Informed of ec w/ attachments:

GPA/IP GPA/SP SECY OGC EDO AE00 Region IV Region V NRR l

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DOCUMENTS PROVIDED BY NRC DURING THE MEETING A copy of the Radiological Assessment System for Consequences Analysis 1.

Code (RASCAL 1.3) provided by AEOD (Incident Response Center)

Nuclear Regulatory Commission Information Digest 1990 Edition 2.

(NUREG 1350, Vol. 2)

Office For Analysis And Evaluation Of Operational Data 1988 Annual 3.

Report, (NUREG 1272. Vol.3, No. I and No. 2) l Operational Experiences at Newly Licensed Nuclear Power Plants 4.

(NUREG 1275, Voi. 1)

Operating Experience Feedback Report Progress in Scram Reduction 5.

(NUREG 1275. Vol. 5) 6.

Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants (NUREG 1150, Vols. I and 2)

ATTACHMENT 1

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3 INFORMATION PROVIDED NRC BY CNSNS b

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CREATION OF CNEN l

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1956 - 1971:

MoST IMPORTANT FACTS:

TLATELOLCO TREATY (1968) l MEXICAN NUCLEAR CENTER ACCELERATOR i

TRIGA MARK-lli REACTOR i

HOT CELLS COMPUTATION CENTER i

CREATION OF INEN l12n- 01

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1972 - 1975:-

BEGINNING OF ACTIVITIES RELATED-

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- SAFEGUARDS AGREEMENT WITH IAEA (1973) 1 1975 - 1979:-

REVISION OF PRELIMINARY' SAFETY' ANALYSIS

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CREATION OF CNSNS,-ININ AND-URAMEX ATOMIC ENERGY COMMISSION 4

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CNEN'S OBJECTIVES:

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ARTICLE 3.-

INEN'S FACULTIES ARE:

1. TO COORDINATE, PROGRAM AND PROMOTE THE PEACEFUL APPL 1-CATION OF NUCLEAR ENERGY IN ORDER TO CONTRIBUTE TO THE DEVELOPMENT...

i VI. TO ESTABLISH, TOGETHER WITH SSA AND OTHER COMPETENT GOVERNMENTAL BRANCH OFFICES -lH ORDER TO CONTROL NU-CLEAR SAFETY-GENERAL REGL.ATIONS FOR THE UTILIZATION

=0F INSTALLATIONS OR ECUIPMENTS CONTAINING RADI0 ACTIVE MATERIALS.

XI.TO PARTICIPATE WITH THE COMPETENT AllTHORITIES IN-THE AUTHORIZATION, INSPECTION AND SURVEILLANCE OF THE AP-PLICATION AND HANDLING OF NUCLEAR FUELS.

Xll.TO AUTHORIZE, INSPECT AND SURVEY THE SITING, DESIGN, CONSTRUCTION AND OPERATION OF NUCLEAR REACTORS.

Xill.TO AUTHORIZE, INSPECT AND SURVEY THE PRODUCTION, POS-SESSION, APPLICATION AND PROFITABLE EMPLOY OF radio-ACTIVE MATERIALS, FOLLOWING-THE TERMS OF THE REGULA-T10NS.

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-0FFICIAL JOURNAL:

JANUARY'26,~1979 y

IN.EFFECT:

JANUARY. 27,:1979

.i TABLE OF CONTENTS l

-CHAPTER 1.

GENERAL j

CHAPTER il.

EXPLORATION, MINING AND. MILLING OF RADIO-j ACTIVE MINERALS.

i CHAPTER.lll..

ATOMIC ENERGY COMMISSSION i

CHAPTER IV.

URAMEX

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UTILIZATION OF NUCLEAR FUELS t

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NATIONAL NUCLEAR RESEARCH INSTITUTE (lNIN)-

CHAPTER Vll.

NATIONAL COMMISSION OF-NUCLEAR SAFETY AND SAFEGUARDS.

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CNSNS'S SAFETY RELATED-FUNCTIONS ARE:

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l. TO ESTABLISH REGULATIONS SO THAT THE SAFETY 0F THE INHABITANTS OF THE COUNTRY MAY.BE GUARANTEED DURING THE DEVELOPMENT OF NUCLEAR INDUSTRY.

i 111. TO REVIEW, EVALUATE AND AUTHORIZE THE BASIS FOR'THE

' DESIGN, CONSTRUCTION, OPERATION, MODIFICATION AND DOCUMENTATION OF NUCLEAR POWER PLANTS AND INSTALLA-

'f TIONS.

V.:TO ESTABLISH NUCLEAR, PHYSICAL AND RADIOLOGICAL SAFE-TY AND SAFEGUARDS REGULATIONS FOR THE APPROPRfATE i

FUNCTIONING OF THE COUNTRY'S NUCLEAR POWER PLANTS AND:

INSTALLATIONS.

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VI. TO ESTABLISH RADIOLOGICAL PROTECTION REGULATIONS FOR THE IMPORTATION AND TRANSPORTATION OF RAD 10 ACTIVE'MA-TERIALS AND SUPERVISE THE DUE' FULFILLMENT OF THE REG-L.

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NUCLEAR. REGULATORY LAW FOR THE CONSTITUTIONAL ARTICLE 27-1 0FFICIA'L JOURNAL:.

FEBRUARY 4, 1985 I N EFFECT:

FEBRUARY 5, 1985 lABLE OF CONTENTS A

. CHAPTER I.-

GENERAL DISPOSITIONS (4 ARTICLES)

CHAPTER 11.

EXPLORATION, MILLING AND MINING OF RADIO-ACTIVE MINERALS (6 ARTICLES)

CHAPTER 111.-

NUCLEAR INDUSTRY (8 ARTICLES)

.CHAPTERIV.

NUCLEAR AND RADIOLOGICAL SAFETY AND PHYS-

'lCAL SECURITY'AND SAFEGUARDS (22 ARTICLES) g CHAPTERLV.

NATIONAL NUCLEAR RESEARCH INSTITUTE (ININ)

(9 ARTICLES)

' CHAPTER VI.

NATIONAL COMMISSION OF-NUCLEAR SAFETY AND' SAFEGUARDS (CNSNS) - (3 ARTICLES) t i

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-1979 1981-NUMBER OF ARTICL5S 39

-52 ARTICLES CONCERNING SAFETY AND.CNSNS 3

3 + 22 NUMBER OF CNSNS'S; FUNCTIONS 7.

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. ESTABLISHMENT'0F REGULATIONS AND PROCEDURES TO.BE' O

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.lT..IS PROVIDED THAT CNSNS IS RESPONSIBLE FOR EVAL-4 UATING!THEEINSTALLATIONS' SAFETY REPORTS, EMERGENCY

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CNSNS IS AUTHORIZED TO KEEP, SECURE OR DEPOSIT RADIO-ACTIVE SOURCES) TO CLOSE TEMPORARILY OR DEFINITIVELY THE INSTALLATIONS THAT:.D0 NOT CORRECT.THEIR DEF!vlEN-lCIES FOR FULFILLING THE REQUIREMENTS.

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ITTIS ESTABLISHED THATITHE HEAD OF SEMIP MAY ORDER LCNSNS-TO TAKE POSSESSION TEMPORARILY-OF.THE INSTAL-t

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CNSNS MOST IMPORTANT ASPECTS (CONT.)

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CNSNS HAS THE RESPONSIBillTY OF COLLECTit4G AllD REMOVING FROM THE RADICACTIVE If4STALLAT10NS, TOOLS, EQUIPMENT, MATERI AL OR Af4Y OTHER CONTAMll4ATED PERS0!4AL PROPERTY.

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CNSNS IS EMPOWERED TO GRANT THE INSTALLATI0llS' AUTHORIZATIONS FOR THE EXTRACTION AND TREATMEl4T 0F RADIOACTIVE Ml!4ERALS (URAN 1UM AND THORlUM)

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CNSNS HAS THE RESPONSIBILITY.OF: ESTABLISHING REQUIRE-MENTS FOR THE TRAINING PROGRAMS OF-THE SAFETY-RELATED

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- RAD 10ACT!VE INSTALLAT10NS.

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LATIONS'S.LICENCES HAS BEEN ADEQUATELY ESTABLISHED.-

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THE REQUIREMENTSfTHAT.:TAKE:INTO ACCOUNT:THE PECULIARITIES h.

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INSPECTIONS - SANCTIONS (1989) i l

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We ostegNO SANCTIONS (85.0%)

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INSPECTIONS STATISTICS (1989) l RIA (8.1 %)

Teletherapy (12.1%)

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Braquitherapy (10.1%)

j Gauges (13.1 %)

i Ophthalmic A. (14.1%)

Logging (2.0%)44

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L lrradiators (1.0%)

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i LICENSES (1989) a

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IRRADIATORS t

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Cs 137 4 SELF SHELDING 6926.4 - TBq i

MEDICINE Cs-137 i SELF-SHELDING 77.7 TBq

- INDUSTRY.

Co-60 1 POOL-TYPE 3466.9 TBq RESEARCH Co-60 1 POOL-TYPE 1831.5 TBq

- 3 SELF-SHELDING 643.8 TBq INDUSTRIAL RADIOGRAPHY l

ENCLOSED 22 ( 72.3 TBq) i PORTABLE 261 (965,7 TBq)

INDUSTRIAL GAUGES 973 (

6.2 TBq)

LOOGING 431 ( 40.0 TBq) g

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TELETHERAPY 1

i.

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IN STORAGE l

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29.6 TBq Cs-137 1

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SOURCES ACTIVITY 9

.444,3 TBq Co-60 204 628.6 TBq Ir-192 -

66 116.3 GBq Cs-137 L 136 162.0 GBq Others.

Am-241 Smoke Detectors 752.4 GBq Kr-85 Electronic Devices 5.8 GBq

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B IMPORTATION OPEN SOURCES l

(1989) t

.l lSOTOPE PACKAGES ACTIVITY Mo-99.

40 11.8 TBq-l-131 -

430 5.i TBq TI206 1190 245.5 GBq

- l-125 17550 22.0 GBq H-3 830 61.0 GBq Others 3919 751.0 GBq i

' TOTAL 23959 Packages 17.98 GBq l

Tc-99M 1089 Generators 22.8 TBq L

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a

THE LAG ~UNA VERDE START-UP EXPERIENCE.

but the were all the time supported by the en-gineers from the Evaluation Departament.

INSPECTIONS AT The effort realized by the Tests Branch people PREOPERATIONAL STAGE OF N"** 'h* P'*"P*'"'I ""I stage, just in the area of mspect. ions, and accord.mg whith year of execu-LAGUNA VERDE.

iion is as follows:

TEAR INSPECTIONS M AN. DAYS Since 1984 CNSNS started a continuos surveil-1984 1 PREOP.

12 lance on the process of systems turnover, first 1985 4*

132 from the organization of Constuction to Start.Up and after 1987 to Operation 1986 6"

339 19S7 5*

112 This surveillance activities have been performed 19S8 3 *(1STUP) 179 1989 27 STARTUP 121 trough several approaches including: resident in.

spector audits, review of test procedures by in-spectors and by evaluators, evaluation of tests As an exemple of the main topics inspected by results and witnessing of tests performance, the Tests Branch engineers, were:

During the utility approach to a important mile.

. Review of Organization and Test Program at stone, like the completion of the construction Preoperational Stage, stage, CNSNS performed a special inspection in which participated about 10 engineers trying to

. Equipment Maintenance during Preoperation-reach several disciplines at a time, this special al phase.

inspections were allways managed by an expert

' from l AEA trough the NRC support. (go Abf Witneesingof tests.

During the period from 1985 trough 1989 CNSN

-Review of Transfer Package for Safety Systems, had the advice of an expert from the IAEA who helped most in the area of nuclear test perfor.

Verification of design as built.

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. mance.

The CNSNS inspectors used as a very useful tool to define the scope and the timing of the inspec-k 34 g (pdg tions the Inspection and Enforcement Manual of the NRC.The inspections during this stage were M hlC b Y M X Cits' performed by the engineers of the Tests Branch,

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INSPECT;lONS DURING THE j.

STARTUP/ OPERATIONAL t

STAGE OF LAGUNA VERDE.

The Laguna Verde Nuclear Power Plant Unit 1 L

statted to load the nuclear fuel on 21 of october of 1988 and with this activity starts the START UP TESTS PROGRAM.

Ilowever the inspection program for this stage

'l

' begins for the CNSNS the year of 19S4, making inspections to the' qualifications of the peopic who was in charge in 1989 to realize the startup tests..

= The general policy of CNSNS in the. area of r

qualifications of its own personnelis to try to get people alleast of the same professionallevel ofIhe people who will recive the inspections; with this in mine it was necesary to sent several people to be qualified as operators' or supervisors for a nuclear power plant. This training was get in Spain, but CNSNS people also has in several oportunities recived in this and another matters training from NRC.

The main topics covered by the inspections in this area have been focoused on: Training and j

qualifications of the people at the control room, Technical Especifications survellances, Organization, qualifications and performance of

Technical Support G roups at and ouside the plant and Quality Assurance during,this Star-I

' tup / Operation phase.

- The effort _ developed by the inspectors of CNSNS (Operations Branch) is as follows:

YEAR INSPECTIONS. M AN DAYS

\\U 1984 3

42 1985:

2 22 1986 7

123-1987 6

150 L

1988 12 324 l.

1989 13 203 r

is

RESUl!.EN DE' EVALUACION POR CNSNS c.s c.

idui.0 DEL EVENTO No. DEL EVENTO No.DE LICENCI A

.i Y'

. SCRAM Provocado por Instrumentaci6n de Nivel NR-1-OP-88 g DEPARTAt! ENTO QUE EWLUA INGENIERO ASIGNADO FECHA DE EVALU ACION CODIFICACION DVO RJMM/ ALM Sept /88

)

[

ANALISIS DEL EVENTO-7 l'

- I..SISTEWAS AFECTADOS 3.. lNFORMAC10N - CONSULTADA Instrumentaci6n Instalada en IR-100 MI-7393 RPS Lecci6n de Tecnologia S..SISTEMAS DARADOS Aparentemente No Existen Sistemas Dahados l

4._RAZON DEL EVENTO SCRAM debido a instrucciones err 6neas en Procedimiento MI-7393.

t i

V' 4

" COMPORTAMIENTO PLANTA / PERSONAL 6..LOS SISTEMAS DE LA CENTRAL ACTUARON CONFORME AL DISENO:

Q St O NO JuSviriQut La instrumentaci6n actuo en forma apropiada SI NO JUSTIF100E G..EL PERSONAL DE LA PLANTA ACTUC EN FORMA EFECTIVA:

. Q SI' NO

-JUSTlF100E Se detect 6 r6pidamente el problema 31 NO-JUSTIFl00E T..lMPACTA A LA SEGURIDAD DE LOS SISTEMAS DE LA CLV : Si.

Debido a que l'os Pro-cedimientos que afectan s'istemas relacionados con la seguridad debe-r r6n de ser escritos en-forma apropiada.

A

" POSICION DE CNSNS PROPUESTA INCLUYENDO ACCIONES CORRECTIVAS La-Revis16n 1 de este evento contiene una mejor descripci6n del mismo, pero es requerido que se detalle claramente la se6a1 que produjo el --

SCRAM ya que aparentemente se provoc6 1/2 SCRAM.

Por otra parte las acciones realizadas son parte del mismo evento, se requiere que establezcan las acciones correctivas pertinentes. En este caso en particular-la instrucci6n de una emis16n instrucc16n especial no es apropiada para evitar el problema.

a NOTA: LA INFORMAC10N DE SOPORTE DEBERA SER ANEXADA INCLUYENDO TODA LA DESCRIPC10N DE 1

~':

L A EVALUACION

<:o_e.

11TL103-ANALISIS DEL REPORTE DE'EVENTO DE LA CLV N' NR-1-0P-88-001 l

-1.-

ANTICEDENTES : El 10 de junio de 1988 a las 16:00 hrs., durante la calibra ci6n/stto. preventivo en los interruptores indicadores de nivel de la vasi-ja LIS-NO36A y LIS-5036C (Rango acplio de -380 cm, a + 150 ca.), se produ jo una perturbaci6n en la instalaci6n de los LIS-N037 A y C del mismo rango de tal manera que so alcanzaron senales de nivel 3 y nivel 1, mismas que --

ocasionaron j scra: del RPS, sub-canales Al y A2 del bus A, e iniciaci6n del RER-A (LPCI) y LPCS que inyectaron agua a la vasija hasta su inhibici6n canual por actuaci6n del operador.

No arranc6 el Generador Diesel Div.1 por estar en libranza.

i 2.-

A%LISIS DE LA INTOF_v.ACION ENV1 ADA POR C.F.E.

2.1 La descripci6n de la causa del evento y del evento en si es limitada para entender con precisi6n cual fue el origen de Este, muestra de -

ello son los siguientes:

I a) LEI Ilenado de los LIS-NO36A y C se 11ev6.a cabo simultineamente o cual de ellos ocasion6 el evento?

b) ISe actuaron otros.LIS's como el NO26 A/C 7 c) LE1 cedio scram del reactor no es ocasionado por las actuaciones de los L1S N024 A-D '

]

d) iQui ocurri6 con otras se5 ales de iniciaci6n (al RCIC y al ADS) per la actuaci6n en Nivel 1 de los LIS-NO37 A/C 7 2.2 Por otra parte revisando las instrucciones del Procedimiento MI-7393 Rev. O, se destaca que ests-limitado en cuanto a cinridad; por ejem-plo:-no indica los nGmeros de vilvulas que el:1nstrumentista tiene -

que operar, no indica cuando abrir la vn1vula de prueba, tarpoco in-cluye precauciones con respecto a otros sistemas comunes, etc.

3.-

CONCLES10NES:

'3.1 La forma de reportar el evento, de conformidad con el PA-0007 - Ane-no 10 REC, no cumple lo establecido para los reportes de evento del licenciatario (LER) estipulado en el KUREG 1022 " Licensee Event 1

I Report Systen".

3.2 Es necesario que la C.F.E. describa en forma mis detallada el evento incluyendo diagramas explicativas, el annlisis. de las anosalias que i

provocaron el evento, el impacto en la seguridad de la: planta y las acciones correctivas exactas que serin tecadas y su fecha de.i= plan-l taci6n.

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1 DOCUMENTS TO BE PROVIDED TO CNSNS BY NRC 1.

Operating Experience Feedback Report - Air Systems Problems (NUREG-1275, Vol.2) 2.

Operating Experience feedback Report - Service Water System Failures and Degradations (NUREG-1275, Vol. 3) 3.

A copy of the Proposed Rule 10 CFR Part 110, Import and Export of Radioactive Wastes (February 7, 1990) 4.

Preliminary Results of the Trial Program for Maintenance Performance Indicators (AE0D/S804A, December 1988) 5 '.~ Application of the NPRDS for Maintenance Effectiveness Monitoring (AE00/S804B, January 1989) 6.

Maintenance Effectiveness Indicater Preliminary Copy, Volume 1, October 1989 (EG&G) 4 7.

Performance Indicators for Operating Commercial Nuclear Power Reactors Report for Fourth Quarter 1989, Part I and Part II (AE00) 8.

Round-Robin Analysis of the Behavior of a 1:6-Scale Reinforced Concrete Containment Model Pressurized to Failure: Posttest Evaluations (NUREG/CR-5341, October 1989,SNL) 9.

Comparison of Analytical Predictions and Experimental Results for a 1:8-Scale Steel Containment Model Pressurized to Failure (NUREG/CR-4209, July 1985, SNL)

-10.

Contacts at the Food and Drug Administration responsible for regulating x-ray machines:

Ed Miller (301) 427-1158-Director, Division of Standards and Enforcement Center for Devices & Radiological Help 1390 Piccard Drive Rockville, MD 20857 or Paul leggett (301) 427-1165 Chief, X-Ray Products Branch (same address as Ed Miller)

'll'.

A copy of the forthcoming videotape on " Good Practices in Preparing and Administering Radiopharmaceuticals" (in preparation by AEOD)

ATTACHMENT 3 4

P

__~~---- - - ___

J ACTIVITIES THAT CNSNS WILL BE INFORMED OF-1 Commission papers and important licensing guidance documents on license 1.

renewal activities.

Date to observe an emergency drill in either Region IV or Region VA rep 2.

(List is enclosed to Attachment 4).

Vera Cruz will also be invited.

Date to observe an internal SALP meeting in Region IV.

i 3.

Date to visit the NRC Operations Center in Bethesda, preferably during a 4.

drill as observers..

Date to attend an Agreement States Annual Meeting.

5.

i

(

l ATTACHMENT 4

)

4 V u ;;, ;<a.

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t FULL-SCALE EMERGENCY EXERCISES.

PROJECTED SCHEDULE Date Exercise Participation 1

)

4/25/90 PaloVerde(PWR).

No NRC Participation i

7/25/90 Cooper (BWR)

No NRC Headquarters Participation --- Full

-Scale RIV Base / Site Teams with' Limited State / Local (NE/MO) 8/29/90 Wolf Creek (PWR)

No NRC Participation Conflict with-Post-Emergency Tabletop '

'9/12/90 WashingtonNuclear2(BWR)

No NRC Participation 10/3/90 Diablo Canyon.(PWR)

No NRC Participation 10/17/90 SanOnofre(PWR)

Full-Scale NRC Region V/_

Headquarters with some State / Local Play

.N0TE: The extent of NRC participation is subject to potential conflicts with the relocation of RV office.-

10/24/90:

Waterford-3(PWR)

Limited Participation RIV Site Team with Base Team Management Interfaces NOTE: This exercise could be escalated to Full-ScaleNRC(HQ) Participation, n

1D3/90 Comanche Peak (PWR)-

Limited-RIV Site Team i

Participation.

(Management a

Interfaces). No State Play. Local Authorities will play.

11/7/90

' Trojan (PWR)

No NRC Participation 11/28/90 FortCalhoun(PWR)

No NRC Participation i

'12/5/90-RanchoSeco(PWR)

No NRC Participation 2/91' RiverBend(BWR)

NRC Participation under l,

review.

L E

7

.