ML17310A710
| ML17310A710 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 10/18/1993 |
| From: | Conway W ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 102-02694-WFC-R, 102-2694-WFC-R, IEB-88-011, IEB-88-11, NUDOCS 9310250291 | |
| Download: ML17310A710 (8) | |
Text
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SUBJECT:
Provides addi info re licensees participation in CEOG evaluation of Pressurizer Surge Line thermal stratification.
DISTRIBUTION CODE:
IE30D COPIES RECEIVED:LTR I
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TITLE: Bulletin 88-11 Pressurizer Surge Line Thermal Stratification ACCELERATFD DOCU1VIENT DISTRIBUTIONSYSTEM
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REGULA INFORMATION DISTRIBUTIO YSTEM (RIDS)
ACCESSION.NBR:9310250291 DOC.DATE: 93/10/18 NOTARIZED: NO FACIL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi STN-50-529 Palo Verde Nuclear Station, Unit 2, Arizona Publi STN-50-530 Palo Verde Nuclear Station, Unit 3, Arizona Publi AUTH.NAME AUTHOR AFFILiATION.
CONWAY,W.F.
Arizona Public Service Co. (formerly Arizona Nuclear ower RECIP.NAME RECIPIENT AFFILIATION Document.Control Branch (Document Control Desk)
NOTES:STANDARDIZED PLANT Standardized plant.
Standardized plant.
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D NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
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WILLIAMF. CONWAY EXECUTIVEVICEPRESIDENT NUCLEAR Arizona Public Service Company P 0 BOX 53999
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PHOENIX. ARIZONA85072-3999 102-.02694-WFC/RAB/ZJE October 18, 1993 U. S. Nuclear Regulatory Commission ATlN: Document Control Desk Mail Station P1-37 Washington, DC 20555
References:
1.
Letter dated July 16,
- 1993, "Safety Evaluation for Combustion Engineering Owners Group Report CEN-387-P, Revision 1,
Pressurizer Surge Une Thermal Stratification Evaluation - Bulletin 88-11" from NRC, to W. F.Conway, Executive Vice President, Nuclear, APS Letter dated April,3, 1990, "Supplemental Response to.NRC Bulletin 88-11, Pressurizer Surge Line Thermal Stratification" from W. F. Conway, Executive Vice President, Nuclear, APS, to NRC
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2, and 3 Docket Nos. STN 50-528/529/530 Additional Information on APS Actions Regarding NRC Bulletin 88-11
'File: 93-055-026 93-056-026 Arizona Public Service Company (APS) participated in the Combustion Engineering Owners Group (GEOG) evaluation of the Pressurizer Surge Line (PSL) thermal stratification.
The final GEOG report was issued and submitted to the NRC in December 1991 (report CEN-387-P, Rev 1).
Action 1.d of NRC Bulletin 88-11, required APS to perform detailed stress and fatigue analyses of the PSL to demonstrate that the integrity of PSLs at PVNGS is maintained for the 40 year design life of these piping systems'The NRC issued its Safety Evaluation Report (SER) regarding the GEOG thermal stratification report, (Reference 1). This SER specifically authorized APS to use the GEOG report results as a basis for the plant specific stress and fatigue analyses required by Bulletin 88-11.
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U. S. Nuclear Regulatory. Commission ANN: Document Control Desk Additional Information on APS Actions Regarding NRC Bulletin 88-11 Page 2 APS has completed the plant specific stress and fatigue calculation (13-MC-ZZ-595). This calculation was based on the GEOG generated data and on the GEOG generic bounding analysis.
The bounding plastic analysis performed by CE was based on PVNGS'SL data which bounded the data from the other 14 participating plants.
The results showed that the highest loads were exerted. at the PSL first elbow in the vertical drop from the pressurizer.
Plastic analysis shows no indication of ratcheting at this loaded elbow.
Similarly, fatigue analysis, of the loaded elbow showed that the maximum usage factor was 0.937. This usage factor (less than.1.0) indicate that the elbow is qualified for the 40 year life of'the plant.
Therefore, APS plant specific calculation-has demonstrated that the integrity of the PSLs at PVNGS is maintained for the 40 year licensed plant life.
Furthermore, APS has established a periodic In Service Inspection Program (ISI) to examine critical PSL'lbow components.
APS has completed Action 1.a of'NRC.Bulletin 88-11, which called for a visual inspection walkdown of PSL.
The inspection results were documented in a letter to the.NRC, (Reference 2).
Regarding Action 1.b of NRC Bulletin 88-11, APS has evaluated the impact of the revised fatigue analysis on postulated pipe break locations in the PSL.
These, locations are shown on Figure 3.6-13 of the UFSAR. APS analysis was conducted in accordance with General'esign Criteria.4.
APS analysis identified two additional postulated pipe break locations at the two elbows immediately above the hot leg.
No adverse impact resulted from these two new locations as there is no plant equipment in the vicinity which affect safe shutdown equipment.
The evaluation results will.be documented in APS calculation (13-MC-ZZ-633), which is, currently scheduled for January 31, 1994.
An UFSAR change is being processed to add'the two new pipe. break locations to the existing five break locations on Figure 3.6-13.
The last action of Bulletin 88-11, Action 1.c, called for obtaining plant data on PSL Thermal Striping, Thermal Stratification, and Line Deflection.
APS obtained -this data through its participation in the GEOG efforts.
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U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Additional Information on.APS Actions Regarding NRC Bulletin 88-11 Page 3 Should you have. any questions, please contact. Richard A. Bernier at (602) 393-5882.
Sincerely, p!
jul WFC/RAB/ZJE/bcf cc:
B. H. Faulkenberry B. E. Holian J. A. Sloan
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