ML20135G647
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DEC 8 1981 Mr. Anthony Refre .
Philippine Atomic Energy Comission P.O. Box 932 Hetro Manila, The Philippines .
Dear Mr. Refre:
l This is to respond to the request for NRC reports which you left with me during your recent visit.
As I infomed you during our discussions, several of the requested reports are management sumary type infomation rather than technical reports.
These reports are NUREG-0020, 0390, 0485, 056f, 0606, and 0748. I am enclosing example copies of each of these reports although in some cases I was unable to provide the specific volume and iumber requested. If the enclosed reports do not meet your needs, please inform me of the specific information contained in the requested volume and number that you have interest in and I can have that portion of the report reproduced ffom ,
microfiche. One report not enclosed is NUREG-0390 Vol. 5. No.1, as it ,
was sent to PAEC on October 5,1981.
I hope the enclosed reports will be helpful to your licensing effort. I i
Sincerely, j Orignal Signed ty Joseph D. LaF1 cur, Jr.
Joseph D.1.afleur, Jr.
Deputy Director Office of International Programs j
Enclosure:
3-page list of reports cc w/ enc 1:
Dr. Zoilo Bartolome
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8509190803 850807 PDR FOIA SCHLEMM 84-559 PDR b n.A :,
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ne ronu ais pa-aomacu oua OFFICIAL RECORD COPY usom i i-m I l
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- 20. NUREG-0020 - Licensed Operating Reactors - Status Su= mary Report (Vol.5,.No.3, March 1981) fd N 1 NUREG-0390 - Topical Report Review Status (Vol.5, No.1)
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NUREG-0485 - Systematic Evaluation Program - Status Su= mary Report
- 23. NUREG10566 - Standards Development - Status Summary Report
- 24. NUREG-OtiO6 - Unresclved Safety Issues Summary (Vol.3, No.2)
- 25. NUREG-0748 - Operating Reactors Licensing Action Summary,
- 26. SECY-80-375 - General Revision of Appendix H and G to 10 QFR 50
- 27. R_.G. 1.144 - Auditi,ng of QA Programs for Nuclear Power Plants - Revised (Oct. 1980) e 9
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' 2 8. NUREG-0491 Safety' Evaluation Report *for'the Preli-minary Design of the Standard Reference System RESAR-414 (Feb. 1979) - -
29 Nureg-0593 Occupational Radiation Exposure (Jan.1981)
- 30. NUREG-0609 Asymmetric Blowdown Loads on PWR Primary Systems (Jan. 1981) o*
- 31. NUREG-0851 Evaluation of Steam Generator Tube Rupture Events (March 1980)
- 32. NUREG-0677 The Probability of. Intersystem LOCA:
Impact Due.to Leak Testing and Operational Changes (May 1980) *
- 33. NUREG-0721 Acceptance Criteria _for the Physi' cal Pro-tection Upgrade Rule Requirements for '
Fixed Sites (Sept. 1980)
- 34. NUREG-0724 Problems in Modelling of Small Break LOCA qE (October 1980)
- 35. NUREG/CR-0773 Training and Qualifying Personnel for -
Performing Measurements for the Control and Accounting.of Special Nuclear Material (Nov. 1!-
- 36. NUREG/CRbO829 A Measurement Control Program for Nuclear Material Accounting (June 1980) ,
- 37. NUREG/CR-0986 The Impact of Decontamination on LWR Radioactive Waste Treatment Systems (April 1980)
- 38. NUREG/CR-0988 Recommendations for Program Development
, for Safety-Related Equipment Qualification .
. Standards and Guides (April 1980) a
, 39. NUREG/CR-1048 Technical Safeguards Issues for Alternative .
Fuel Cycles (Sept. 1980) ,
- 40. NUREG/CR-1063 Performance Testing of Personnel Dosimetry-Services: Procedures Manual (Oct. 1977-Sept. 1979)
- 41. NUREG/CR-1152
' Recommended Msthods for Estimating' Atmos-pheric Concentrations of Hazardous.Va'pors After Accidental Release Near. Nuclear Reactor Sit'es (April 1980) ,
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,- ,4 2'. NUREG/CR-1345 Nuclear' Power Plant Design Concepts for Sabotage Control, Vol.2 (Jan. 1981) i
- 43. NUREG/CR-1380 Assessment of Curre,nt Onsite Inspection Vol.2 Techniques for Light-Water Reactor Fuel Systems (Jan. 1981) 44 NUREG/CR-1546 Management of Radioactive Waste Gases from the Nuclear Fuel ~ Cycle: Comparison of Alternatives (Feb. 1981)
- 45. NUREG/CR-1610 Inspection Methods for Physical Protection Vol.1, No.2 Project (Feb. 1981) , .
46.
NUREG/CR-1645 The- PWR Loss-of -Coolant Accident, Analysis Capabilitj of the WRAP-FM System (Jan. 1981)
- 47. NUREG/CR-1 6 82 El,ectrical Insulators in a Reactor Accident Environment (Jan. 1981) 4 8. . NUREG/CR-1781 Assessment of Methods for Evaluating Adequacy of Physical Protection Sy'tems s (Feb. 1981)
- 49. NUREG/CR-1783 Structural Integrity of Water Reactor
- Pressure Boundary Components (Feb. 1981) .
- 50. NUREG/CR-1811 Nuclear Reactor Safety (Jan. 1981)
- 51. NUREG/CRb1818 . ~Fuel Performance Annual Report for 1979 (Jan. 1981) ,
- 52. NUREG/CR-1831 Hydrogen Distribution After Loss-of- .
- Coolant Accident in the Subdivided Con-tainment of Light Water Reactors (Feb. 1981) i
- 53. NUREG/CR-1880 ' Initial Quantification of Human" Errors
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Associated with Reactor Safety System .
Components in Licensed Nuclear Power !
, Plants (Jan. 1981) l
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