ML20246F365
| ML20246F365 | |
| Person / Time | |
|---|---|
| Issue date: | 08/17/1989 |
| From: | Chan T Office of Nuclear Reactor Regulation |
| To: | Spond D BABCOCK & WILCOX OPERATING PLANTS OWNERS GROUP |
| References | |
| IEB-88-011, IEB-88-11, NUDOCS 8908300288 | |
| Download: ML20246F365 (4) | |
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-!; 7 . August 17, 1989 Mr. Daniel F. Spond-Babccck & Wilcox Owners Group 1700 Rockville Pike, Suite 525 Rockville, Maryland 20852
Dear Mr. Spond:
SUBJECT:
NRC Bulletin 88-11, " Pressurizer Surge Line Thermal Stratification" #
In response to NRC. Bulletin 88-11, a number of the B&WOG membership provided their bounding analysis for the pressurizer surge line via B&WOG report BAW-2085, " Pressurizer Surge Line Thermal Stratification" dated May 1989. L
.The staff reviewed the report and determined that additional information was recuired.
i 'The requested information is identified in the Enclosure to this'
'. letter.
- l. To facilitate our review, the requested information was discussed during a July 13,1989 telecon with the B&WOG with the understanding that formalized responses.to the questions would be needed.
The' purpose of this letter is to document, our request for additional information.
(' We a s that the;infc mation requested by the Enclosure be provided within 30 i days: from receipt e ;his letter, or provide an alternate schedule for doing j so within 15 days. '
The reporting and/or recordkeeping requirements of this letter affect fewer
.than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely, original signed by i
Terence L. Chan, Senior Project Manager Project Directorate V Division of Reactor Projects - III, IV, Y and Special Projects 1 Office of Nuclear Reactor Regulation i l
1 cc: James H. Taylor l Nuclear Power Division PKuo 1 Babcock & Wilcox Co. Shou i P.O. Box 10935 TKenyon i Lynchburg, VA 24506-0935 DISTRIBUTION TChan
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\ , . ,* , * #' August 17, 1989 Mr'. Daniel F. Spond l
Babcock & Wilcox Owners Group-1700.Rockville Pike, Suite 525 Rockville, Maryland 20852
Dear Mr. Spond:
~
SUBJECT:
NRC Bulletin 88-11, " Pressurizer Surge line Thermal Stratification" In' response to NRC Bulletin 88-11, a number of.the B&WOG membership provided
- their bounding' analysis for the pressurizer surge line via B&WOG report' BAW-2085, " Pressurizer Surge Line Thermal Stratification" dated May 1989.
The' staff reviewed the report and determined that additional information was-required. The requested'information is identified in the' Enclosure to this letter..
To facilitate our review, the requested information was discussed during a July 13, 1989 telecon with the B&WOG with the understanding th6t formalized responses to the questions would be needed.
The purpose of this letter is to document our request for' additional information.
We ask that the-information requested by the Enclosure be provided within 30 days from receipt of this letter, or provide an alternate schedule for doing so within 15 days.
The reporting and/or recordkeeping requirements of this letter affect fewer than ten. respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincer ly, ,
ya ./ =m -
T rence L. Chan, Senior Project Manager Project Directorate V Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation cc: ' James H. Taylor Nuclear Power Division
.Babccck & Wilcox Co.
'P.O. Box 10935 .
Lynchburg, VA .24506-0935
~
.y ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION Pressurizer Surge Line Thermal Stratification Review of BAW - 2085 Dated May 1989 GENERAL
- 1. Provide a comparison of calculated surge line thermal displacements with the measured Oconee data to demonstrate the validity and conservatism of the bounding analysis.
- 2. Discuss the B&WOG's efforts regarding the effects and generic implications of potentia ^i thermal stratification on other lines which may be suscept-ible to this phenomenon.
Section 4.0
- 1. How do the monitoring results for displacements and temperatures compare with analysis results? What are the values at the critical locations?
- 2. Since no upsets or cooldowns have occurred yet, what were the assumptions /
inputs used in the analysis? How was the worst case determined?
Section 5.0
- 1. What are the key assumptions /inp;ts provided by Toledo Edison to B&W for the fatigue analysis of Lavis-Besse?
- 2. What are the specific differences between the Muelheim-Kaerlich (M-K) plant and the domestic plants?
- 3. What is the basis for loading case I to occur three times?
(Ref. page 5-2).
- 4. What are the usage factor values at critical locations a) due to stratification loadings?
b) due to other loadings? .
- 5. How are the usage factors combined at critical locations a) linearly?
b) enveloped?
- 6. How are the values for the allowable number of cycles shown on page 5-4 determined? Do they include striping effects? If not, what is the l impact?
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Section'5.0 Continued
-7. ; What type of adjustments.and for which data were made to the M-K plant to account for the differences of Davis-Besse?
- 8. What'are the maximum values and worst case location for ASME III NB-3600 equations 9 thru 14? What is the effect if 3Sm allowable value is used?
- 9. The use of twice " strain-hardened" yield strength in place of the 3Sm limit required by the ASME Code may be non-conservative. The acceptable interim limit is twice yield strength based on CMTR values.
Section 6.0-1.. Are the snubbers shown on Figs. 6.1 and 6'.2.the only suppor'ts in the entire PSL7 If not, provide type and location of other supports.
Section 7.0
- 1. How will the measurement program from Oconee provide input to the striping effects? (Temperatures at the inside face of the pipe wall can't be measured unless they are of a large amplitude and a long period).
- 2. ' Why are 240 cycles used for Davis-Besse instead of 3607
- 3. In ref. to Table 7-2" a) Does the temperature range account for insulation?
b) What kind of stress concentration / indices are t sed?
Appendix "A" Need clarif1ca. ion for first paragraph of page A-4 Appendix "B"
- 1. What is the % difference; and what are the values for displacements, reactions and stresses, when the non-linear vs equivalent linear temperature profiles F.E. models are compared?
- 2. How are the peak stress ranges scaled down to match the actual data from the Oconee measurements?
- 3. What is the usage factor contrit,ution from each item (1-4) described on page B-3?
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