ML20244E533
| ML20244E533 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/31/1986 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Pastis H Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20244D710 | List:
|
| References | |
| TAC-62174, NUDOCS 8701020201 | |
| Download: ML20244E533 (12) | |
Text
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4 Ref. 13 e nog'o, UNITED STATES
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j NUCLEAR REGULATORY COMMISSION i
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-l W ASHINGTON, D. C. 20555
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DECEMBER 31, 1986 Docket Nos.: 50-269, 50-270 and 50-287
' MEMORANDUM FOR:
Helen Pastis, Project Manager PWR Project Directorate No. 6 Division of PWR Licensing-B FROM:
Dennis M. Crutchfield, Assistant Director Division of PWR Licensing-B
SUBJECT:
OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3..
EXEMPTION TO 10 CFR 50, APPENDIX J. AND CHANGE OF THE TECHNICAL SPECIFICATION (TAC N05. 62174, 62175AND62176)
Reference:
Letter from Hal B. Tucker (Duke Power Company) to Harold R. Denton dated August 13, 1986 As requested, Section B of the Engineering Branch, DPLB, reviewed the reference and its enclosures I.and II. Based on the review the staff finds that the licensee's request regarding exemption from 10 CFR 50 Appendix J is acceptable and therefore recommends that the licensee's request be granted.
Our Safety Evaluetion Report is enclosed.
Since there is likelihood that Appendix J and the regulatory standards pertinent to the CILRT will be revised, the staff considers it to be prudent to restrict this exemption to the testing only, without revising the Technical Specifica-tion. The Technical Specification may be revised at a later date when the appropriate regulations are officially approved.
3.
ennis M. Crutchfiel, As istant Director Division of PWR Lic nsing-B l
Enclosure:
As stated l
cc:
J. Stolz W. J. Olmstead R. Ballard B. D. Liaw R. Bosnak W. Regan 2
J. Pulsipher e
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l G. Arndt CONTACT:
R. Lipinski, DPLB/EB 49-29433
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. DUKE POWER COMPANY OC0t'EE NUCLEAP. STATION, UNITS 1, 2 AND 3-REQUEST FOR EXEMPTION TO 10 CFR 50 APPENDIX J AND CHANGE OF THE TECHNICAL SPECIFICATION (TAC N05. 62177,-62178 AND 62179) i '
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1.0 BACKGROUND
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The Code of Federal Regulations,10 CFR 50.54(0) specifies that primary
' reactor containments for water' cooled power reactors shall comply with Appendix J, " Primary Reactor Containments Leakage Testing for Water-Cooled-
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Power Reactors." Appendix J incorporates by reference ANSI Standard N45.4-1972, " Leakage Rate Testing of Containment Structures'for Nuclear Reactors." This~ standard requires that containment leakage. calculation be perfomed using either the Point-to-Point method or the Total. Time method. It is also indicated in this Standard that the Point-to-Point method is more applicable to uninsulated containments where atmospheric stability is affected by outside diurnal changes, while the Total Time method.ismoreapplicabletoinsulated(forexample, concrete) containments, that are relatively unaffected by diurnal changes.
In 1976 a comparison was made of the results of test analyses that were perfomed using Point-to-Point, Total Time, and Mass-Plot (or Mass-Point) techniques.
("ContainmentLeakRateTesting: Why the Mass-Plot Analysis Method is Preferred," Power Engineering February 1976). A revision to ANSI /ANS Standard 56.8-1981 " Containment System Leakage Testing" specifies the use of Mass-Plot, to the exclusion of the two older methods. A proposed revision to Appendix J, which has been published for public comment i
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l (Proposed Rules, Federal Register Volume 51, No. 209, October 29,1986),
incorporates the new Standard.
On August 1, 1986 Duke Power C'ompany was notified via telephone that Mass-Plot method was not in conformance with the current Appendix J and was therefore invalid. Pending the revision of Appendix J which incorporates
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the Mass-Plot analysis, licensees who wish to use the Mass-Ploi. techniques must submit an application for exemption from the Appendix J requirement that Containment Integrated Leak Rate Tests (CILRTs) will conform with ANSI-N45.4-1972 2.0 LICENSEE'S JUSTIFICATION FOR EXEMPTION By letter of August 13, 1986, the licensee requested an exemption from 10 CFR 50, _ Appendix J. Paragraph III.A.3, which requires that all Type A Containment Integrated Leak Rate (CILR) Tests be performed in accordance with ANSI N45.4-1972, " Leakage Rate Testing of Containment Structures for
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Nuclear Reactors." ANSI N45.4-1972 requires that leakage calculations be performed using either the Total Time method or the Point-to-Point method.
The licensee indicated that in 1976 the staff recognized the merits of the Mass-Plot technique and that this method became the staff recommended methor to use. On that basis Duke Power has been performing calculations
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using'the Mass-Plot method. While in the process of perfoming the leak-rate tests Duke was informed by the NRC that the 1976 staff position with regard to the Mass-Plot method is not in accordance with the current provisions of 10 CFR 50, Appendix J, and is therefore invalid. Duke Power has therefore provided the following arguments in support of the applica-tion for exemption from Appendix J:
a)
The Mass-Plot method is a more accurate method of calculating containment leakage, and' b)
The proposed amendment does not present a significant hazard, as defined by the NRC regulations in 10 CFR 50.92.
S.0 EVALUATION OF THE REQUEST The basis for the licensee's request is paragraph 10 CFR 50.12(a)(2)(ii) which states that the application of the regulation in the particular circumstances is not necessary to achieve the underlying purpose of the rule, i.e., to provide an accurate and conservative test of containment integrity.
The licensee also indicated that according to paragraph 50.12(a)(2)(vi) there is present " material circumstance." which was not considered when the regulation was adopted, which exists by the fact that the Mass-Plot analysis was initiated and conducted at Oconee with the i
knowledge and upon the recommendation of the NRC staff. Although the staff could not find any formal confirmation of the approval of the i
Mass-Plot analysis by the NRC, it is believed that at the time of its. intro-duction to the industry, the s'taff recognized its merits in calculating leakage rates.
It has been recognized by the professional commurity that the Mass-Plot method is superior to the two other methods, Point-to-Point and Total Time, which are referenced in ANSI N45.4-1972 and endorsed by the present regulations. The Mass-Plot method calculates the mass at each point in time, and plots it against time. A linear regression line is plotted through the mass time points using a least square fit. The slope of this line is the leak rate. The staff believes that the Mass-Plot method was not specified in ANSI N45.4-1972 because the other more conservative methods (Point-to-Point bnd Total Time) were adequate and suitable for the sensitivity levels of the instrumentation in use at that time. However, with the present developments in technology the Mass-Plot method has gained recogni-tion as the proper one to use.
The superiority of the Mass-Plot method becomes apparent when it is compared with the two other methods.
In the Total Time method a series of leakage rates are calculated on the basis of air mass differences between an initial data point and each individual data point thereafter. If for any reason (such as instrument error, lack of temperature equilibrium, ingassing or outgassing) the initial data point is not accurate, the results of the test will be affected.
In the
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e Point-to-Point method the leak rates are based on the mass difference between each pair of consecutive points which are then averaged to yield
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.a single leakage rate estimate. Mathematically, this can be shown to be the difference between the air' mass at the beginning of the test and the air mass at the end of test expressed as a percentage of the containment air mass.
It follows from the above that the Point-to-Point method ignores any mass readings during the test and thus the leakage rate is calculated on the basis of the difference in mass between two measurements taken at the beginning and at the end of the test, which are 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> apart.
The present position of the staff is formulated.in the " Draft Regulatory Guide and Value/ Impact Statement," published for comment, dated October 1986, which with exceptions endorses the ANSI /ANS Standard 56.8-1981.
Furthermore, it recommends the Extended ANSI Method which is basically the Mass-Plot method with two additional conditions pertaining to the quality of the regression fit obtained using the Mass-Plot method. Condition 1 represents a limit on the deviations of the data points from a straight line.
Condition 2 provides a limit on the scatter of the data points about the regression line.
As stated above, Appendix J to 10 CFR 50 is being revised and the proposed Regulatory Guide has been published for connents. The staff believes that it is premature to change the Technical Specification at this time and there-fore the licensee's request in this regard should be denied.
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4.0 CONCLUSION
Based on the above' discussion, the staff finds that the licensee's request i
for exemption from 10 CFR 50, tppendix J, is acceptable.
In view of the fact that Appendix'J is,being revised and the new Regulatory Guide addressing methodology of CILRTs has been published for comments the staff considers that it is. prudent at this time to restrict this exemption to the test itself without pennitting the revision of the Technical Specification which would
. include the Mass-Plot technique for analyzing the CIRLT results. Revision.
of the Technical Specification should be deferred to the resolution of the appropriate regulatory criteria.
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- SALP REPORT E
PLANT:=0conee l', 2, and 3 LICENSEE: Duke Power Company, v.
' DOCKET NO.:'50-269, 50-270 and REVIEWER:
P. N.~Randall 50-287_
LICENSING ACTIVITY: Exemption 7
EVALUATION CRITERIA RATING REMARKS-1.
Management Involvement 1
and Control in Assuring' Quality
' 2. -
Approach to Re' solution.
1 E
of ";chnical Issues from.
a : iety Standpoint.
3.
Responsiveness to NRC 1
' Initiatives 4.
Enforcement History.-
NA i
5.
Reporting and Analysis NA of Reportable Events 6.
Staffing NA
.The summary SALP rating for this submittal is 1.
The Licensee-provided adequate information with the entry document.
This information was so complete that there was no need to request additional information in order to fulfill this task.
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c ANSI N45.4-1972 bat eru can Yacl Joe h ere f kO}e: kkfort was Coff t*}kteol h y
19n and conno+ be procested' Lu k puobcs OM'S in 1{ cofy is rieeded fle a se Corr fact " 14mee sca n r)uclear $odelI The neo<+ cowsh of is pges s
American National Standard Leakage-Rate Testing of Containment Structures for Nuclear Reactors m.
Sponsor American Nuclear Society l
Approved March 16,1972 American National Standards Institute 4
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