ML17297B748
| ML17297B748 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 10/29/1982 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Novak T Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0857, RTR-NUREG-857 ANPP-22153-ACR, NUDOCS 8211020367 | |
| Download: ML17297B748 (15) | |
Text
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'ACCESSION NBR:8211020367 DOC ~ DATE: 82/10/29 NOTARIZED; YES FACIL:STN"50 528 Palo Verde Nuclear Station~
Unit 1E Arizona Publi STN 50-529 Palo Verde Nuclear Stations Unit 2P Arizona Publi STN"50-530 Palo Verde Nuclear StationP Unit 3~ Arizona Publi AUTH,NAME AUTHOR AFFILIATION VAN BRUNTiE ~ ED
, Arizona Public Service Co ~
RECIP ~ NAME RECIPIENT AFFILIATION NOVAKET ~ MD Assistant Dir actor for Licensing
SUBJECT:
Forwards marked up FSAR pages w/results of analyses demonstrating ability of fuel design to withstand combined seismic 3,
LOCA loadsiresolving open item in SER Section 4 ~ 2,1 ~ Info will be included in future FSAR amend.
DISTRIBUTION CODE:
SOOIS COPIES RECEIVED:LTR L ENCL g
SIZE:
TITLE: Licensing Submittal; PSAR/FSAR Amdts L Related Correspondence NOTES:Standardized plant.
Standardized plant
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DOCKET 05000528 05000529 05000530 05000528 05000529 05000530 RECIPIENT ID CODE/NAME NRR/DL/ADL NRR I.B3 LA INTERhAL: ELD/HDS3 IE/OEP EPDS 35 NRR/DE/AEAB NRR/OE/EQB 13 NRR/DE/HGEB 30 NRR/DE/MTEB 17 NRR/DE/SAB 2Q NRR/DHFS/HFEB00 NRR/DHFS/OLB 34 NRR/DS I/AEB 26 NRR/DSI/CPB 10 NRR/DS I/ETSB 1?
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'HOENIX'RI2ONA85036 October 29, 1982 ANPP-22153 - ACR/NFQ Mr. T. 3P. Novak Assistant Director for Licensing Division of Licensing Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.
C.
20555
Subject:
Palo Verde Nuclear Generating Station (PVNGS) Units l, 2 and 3
Docket Nos.
STN-50-528/529/530 File:
82-056-026'.1.01.10
References:
1.
NUREG-0857, "Safety Evaluation Report" related to the Operations of Palo Verde Nuclear Generating Station Units 1, 2 and 3, dated
- November, 1981 2.
PVNGS FSAR Section 4A.1 (NRC question 490.1)
Dear Mr. Novak:
Section 4.2.1 of the PVNGS
- SER, (Reference (1)), provides the following open item discussion:
"As a result of the staff review of CENPD-178, CE has submitted a revised version of CENPD-178.
The staff, although it has not commenced review of this revised report, concludes that the report should be applicable to PVNGS 1-3 and conform to the requirements of NUREG-0609, and hence, the requirements of Appendix A of SRP Section 4.2.
The applicant should, there-fore, provide the results of an analysis that uses this revised method and demonstrates the ability of the Systems 80 fuel design to withstand combined seismic and LOCA loads at the PVNGS site.
The applicant must also demonstrate that all CESSAR interfaces are acceptably.
addressed in the analysis.
The staff will report on the resolution of this outstanding issue in a later report".
Attachment (1) provides the results of the analyses that uses the CENPD-178, Revision 1, method which demonstrates the ability of the PVNGS fuel design to withstand combined seismic and LOCA loads at the PVNGS site and demonstrates that the CESSAR interfaces are met.
This information will be incorporated into a future FSAR amendment (section 4.2.3 and 4A.1)
'211020367 821029 PDR ADOCK 05000528 E
b
Mr. T. H. Novak October 29, 1982 ANPP-22153 ACR/1jFQ Page 2
We believe this information adequately resolves the SER section 4.2.1 open item.:. Please contact me if you have any further questions.
Very truly yours, WUA E. E. Van Brunt, Jr.
APS Vice President Nuclear Projects ANPP Project Director EEVBJr/WFQ/sp Attachment cc:
E. Licitra L. Bernabdi P. Hourihan A. Gehr
STATE OF ARIZONA
)
)
as'OUNTY OF MARICOPA)
I, Edwin E. Van Brunt, Jr., represent that I am Vice President Nuclear Projects of Arizona Public Service Company, that the foregoing document has been signed by me on behalf of Arizona Public Service Company with full authority so to do, that I have read such document and know its contents, and that to the best of my knowledge and belief; the statements made therein are true.
~~I n.~
Edwin E. Van Brunt, Jr.
, 1982
~
My Commission expires:
~My'ommission Expires May 19, 1980 Sworn to befo're me this 2.Q day of Gc+o4 Notary Public
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PVNGS FSAR QUESTION 4A.i (NRC Question 490.1)
APPENDIX 4A (4.2.3)
We note that the PVNGS'SAR references Section 4.2.3.1.2 of the CESSAR FSAR, which in turn references the use of the analytical methodology from the C-E topical report CENPD-178.
This report has not been approved for licensing applications and is currently undergoing revision.
By letter dated March 23,
- 1981, C-E has projected the submittal of the revised report to be in the second quarter of 1981.
We anticipate that the revised report will present methods that conform to the requirements of NUREG-0609.
However, plant-specific results using these methods will be needed for PVNGS.
The PVNGS FSAR should thus provide the results of an analysis that demonstrates the ability of the Systems 80 fuel design to withstand combined seismic-and-LOCA loadings at the PVNGS site in accordance with the requirements of NUREG-0609.
RESPONSE
This report was revised in response to a Round Zero question asked on the CESSAR docket, STN-50-470, on Nash
$3, 397).
The qethodg, delineated in the revised applied to PVNGS to obtain plant. specific seismic and LOCA combined loading structural analysis; 7'.
,8@8lysw. /88ulfs, 48E+PnUiNEJ Nf /mEpJzJ seafio~ 4 4 8 I.
easement.
Il t"" Q"""""
(4.5)
What means will be used to provide continuing assurance that the reactivity invested in the water-soluble B C-filled control element assemblies is maintained'?
For other applications (e.g.,
ANO-2 and SONGS-2S3),
the CEA symmetry test that is described in Section 14.2.12.4 of the CESSAR FSAR was found to be an acceptable method of providing this assurance, on the basis that October 1981 4A-1 Amendment 6
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PVNGS FSAR 4.2 FUEL SYSTEM DESIGN Refer to'CESSAR Section 4.2.
4.2.1 DESIGN BASES Refer to CESSAR Section 4.2.1.
4.
2.2 DESCRIPTION
AND DESIGN DRAWINGS Refer to CESSAR Section 4.2.2.
4.2.3 DESIGN EVALUATION Refer to CESSAR Section 4.2.3.
~ ~ 488+ A.~
eadment.
AR 4.2.4 TESTING AND INSPECTION PLAN Refer to CESSAR Section 4.2.4.
PVNGS guide PVNGS prior will verify actual guide tube wear rates by measuring tube wear during the first refueling outage for Unit 1.
will submit an inspection plan for NRC approval six months to the first refueling outage for Unit 1.
4.2.5 CESSAR REACTOR INTERFACE REQUIREMENTS The following interface requirements are repeated from CESSAR Section 4.2.5:
Below are detailed the interface requirements that the reactor places on certain aspects of the BOP, listed by categories.
In addition, applicable GDC and Regulatory Guides which C-E utilizes in its design of the reactor are presented.
The GDC and Regulatory Guides are March 1982 4.2-1 Amendment 8
~
I
4.2.3. I Seismic and LOCA Seismic and LOCA evaluation of the fuel assembly are performed on the basis of specific Palo Verde site information.
In this regard, information regarding plant specific seismic and LOCA effects on the fuel assembly is discussed in the following subsections:
4.2.3.1.1 Operating Basis Earthquake (OBE)
During the postulated OBE, the fuel assembly is subjected to lateral and axial accelerations which, in turn, cause the fuel assembly to deflect from its normal shape.
The method of c'alculating these deflections is described in Subsection 3.7.3. 14 of CESSAR.
The magnitude of the lateral deflections and resultant stresses were evaluated for acceptability.
The method for calculating stresses from deflected shapes is described in Reference 1.
The results of the stress analysis demonstrate that the component stresses are less than the allowable values discussed in Subsection 4.2. 1. 1 of CESSAR.
4.2.3. 1.2 Safe Shutdown Earthquake (SSE)
The axial and lateral loads and deformation sustained by the fuel assembly during a postulated SSE have the same origin as those discussed above for the OBE, but they arise from initial ground accelerations twice those assumed for the OBE.
The analytical methods used for the SSE are identical to those used for the OBE.
The predicted component stresses were less than the allowable values discussed in Reference l.
4.2.3.1.3 Loss of Coolant Accident (LOCA)
In the event of a large break LOCA, there will occur rapid changes in pressure and flow within the reactor vessel.
Associated with the transient are rela-tively large axial and lateral loads on the fuel assemblies.
The methods used for analysis of LOCA loads and stresses are described in Reference I-The results of the'1'OCA analysis were that component stresses were within the limits established in Reference 1.
4.2.3.1.4 Combined SSE and LOCA It is no't considered appropriate to combine the stresses resulting from the SSE and LOCA events.
Nevertheless, for purposes of demonstrating margin in the
- design, the maximum stress intensities for each individual event were derived by a square root of sum of the squares (SRSS) method.
This was performed as a function of fuel assembly evaluation and position, e.g.,
the maximum stress intensities for the center guide tube at the upper grid elevation (as determined in the analysis discussed above in the SSE and LOCA subsections) were combined by the SRSS method.
The results 'demonstrated that the allowable stresses
p'v Zeue7A PALO VERDE FSAR + 2 3 described in Reference 1 were not exceeded for. any posi.tion-.along the fuel assembly, even under the added conservatism provided by this load combination.
NOTE:
Reference 1:
"Structural Analysis of Fuel Assemblies for Seismic and Loss of Coolant Accident Loadings,"
Combustion Engineering, Inc.,
CEi<PD-178-P, Revision 1, August, 1981.
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