ML20209C326
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NUCLEAR REGULATORY COMMISSION
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9' p Docket Nos.: 50-275 AUG.1 1983
[Q 50-323 D*
MEMORANDUM FOR: Thomas M. Novak, Assistant Director f,
for Licensing
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Division of Licensing FROM:
Daniel R. Muller, Assistant Director for Radiation Protection h-Division of Systems Integration
SUBJECT:
EVALUATION OF INDEPENDENT DESIGN VERIFICATION PROGRAM (IDVP) REVIEW 0F THE EQUIPMENT QUALIFICATION METHODOLOGY USED BY PG&E FOR EQUIPMENT LOCATED OUTSIDE CONTAINMENT (TAC. #48045)
The Accident Evaluation Branch evaluated the IDVP contractor's review of the post LOCA radiation environment used in the specification for safety related equipment outside containment for Diablo Canyon as reported in Interim Technical Report 19 (Revision 0).
The service-related contractor reviewed equipment qualification radiation dose calculations at two locations; one location was associated with the Auxiliary Feedwater (AFW) system, while the other was associated with the Control Room Ventilation and Pressurization (CRVP) system. The review was restricted to equipment qualification doses due to post-LOCA recirculation outside containment used for the specification of qualification of safety-related equipment. The service-related contractors involved in the radiological analysis under the direction of PG&E were the following:
RadiationResearchAssociates(RRA)
EDS Nuclear, Inc. (EDS)
RRA performed all source and dose calculations. EDS supplied source geometry, source parameters, and concrete shield data to RRA and also prepared the Diablo Canyon Radiation Shielding Review Report.
The RRA job records, EDS input, and PG&E information were reviewed by the service-related contractor for correct selection and incorporation of design input into the analyses, reasonableness of assumptions used in calculations, correctness of design interface infonnation used in analyses, adequacy of design or calculational method used, and reasonableness of the output, compared to the input.
The service-related contractor performed a calculation of the sensitivity due to different calculational methods to develop acceptance criteria for the comparison of results of the independent calculations of dose at the location in the AFW system and at the location in the 9(bW8I h f L..
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Thomas M. Novak.
CRVP system. Using identical input data, the difference in output of the various computer programs was determined. The ORIGEN program was compared against the ACTIVITY 2 and RADI0 ISOTOPE programs; RRA QADMOD was compared against SWEC QADM00. Finally, an overall comparison was made to determine the composite difference of the results derived from the programs.
Verification of doses presented in the Diablo Canyon Radiation Shielding Review Report was made by the service-related contractor by independently calculating the integrated doses at one point in the AFW system and at one point in the CRVP system. The results of this calculation were compared to RRA results, using the acceptance criteria developed in the sensitivity calculation.
Verification that RRA and SWEC geometric models were developed from.
drawings which adequately reflected the "as-built" conditions of the plant was accomplished by a site inspection of the areas of interest.
These areas are the GE area of the Auxiliary Building, the RHR heat exchanger area, and the control room ventilation area.
Although the IDVP contractor's Interim Technical Report 19 (Revision 0) provides very little information as to the basic assumptions utilized in the review, the methodology that is provided appears to follow the guidelines in NUREG-0588, and the method of review was very thorough.
Therefore, AEB concludes that the IDVP review would not conflict with the NRC findings during the OL review and there are no generic concerns.
We note, however, that a critique of the application of acceptable methodology by the applicant to establish specific values of radiation doses was not provided in the IDVP report and, therefore, radiation environments cannot be verified.
If you have any questions in this matter contact Larry Bell at X28024.
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Daniel R. Mull
, Assistant Director for Radiation Protection Division of Systems Integration cc:
R. Mattson l
V. Noonan H. Schierling J. Wemiel i
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