ML17298B566
| ML17298B566 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 12/04/1984 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| ANPP-31312-WFQ, NUDOCS 8412060001 | |
| Download: ML17298B566 (10) | |
Text
REGULATORY i FORMATION DISTRIBUTION SY~
M (RIDS)
ACCESSION NBR;8412060001 DOC ~ DATE: 84/12/04 NOTARIZED;" YES FACIL:STN 50 528 Palo Verde Nuclear Station~
Unit ii Arizona Publi STN 50 529 Palo Verde Nuclear Stationi Unit 2i Arizona Publi STN-50-530 Palo Verde Nuclear Stationi Unit 3i Arizona Publi AUTH,NAME AUTHOR AFFILIATION.
VAN BRUNTgE.E, Arizona Publjc Service Co ~
RECIP,NAME RECIPIENT AFFILIATION KNIGHTONiG AH+
Licensing Branch
SUBJECT:
Forwards addi FSAR changes resulting from rev to,shutdown cooling sys design prcssure'hanges address sys relief, valves set pressure (setpoint) increase from 435 psig to 467 psig, DISTRIBUTION CODE:
B001D COPIES RECEIVED;LTR ENCL SIZE:
TITLE'. Licensing Submi ttal:
PSAR/FSAR Amdts 8, Rel ated Cot r espondence NOTES:Standardized plant ~
Standardized
- plant, Standardized plant ~
DOCKET 05000528 05000529 05000530 05000528 050005?9 05000530 RECIPIENT ID CODE/NAME NRR/DL/ADL NRR LB3 LA INTERNAL; ACRS 41 ELD/HD$3 IE/DEPER/EPB 36 IE/DQASIP/QAB21
'RR/DE/AEAB NRR/DE/EHEB NRR/DE/GB 28 NRR/DE/MTEB 17 NRR/DE/SGEB 25 NRR/DHFS/LQB 32" NRR/DL/SSPB NRR/DS I/ASB NRR/DSI/CSB 09 NRR/DSI/METB 12 S
AB 22 G
F ILE 04
/MIB EXTERNAL: BNL (AMDTS ONlY)
FEMA REP DIV 39 NRC PDR 02 NTIS COPIES LTTR ENCL 1
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0 RECIPIENT ID CODE/NAME NRR LB3 BC LICITRAgE 01 ADM/LFMB IE FILE IE/DEPER/IRB 35 NRR ROEgM ~ L NRR/DE/CEB 11 NRR/DE/EQB 13 NRR/DE/MEB 18 NRR/DE/SAB 24 NRR/DWFS/HFEB40 NRR/DHFS/PSRB NRR/DS I/AEB 26 NRR/DS I/CPB 10 NRR/DS I/ICSB 16 NRR/DS I/PSB 19 NRR/DSI/RSB
?3 RGN5 DMB/DSS (AMDTS)
LPDR 03 NSIC 05 PNL GRUELzR COPIES LTTR ENCL' 0
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LTTR 54 ENCL 46
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gt
Arizona Public Service Company Director of Nuclear Reactor Regulation Attention:
Mr. George W. Knighton, Chief Licensing Branch No.
3 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555 December 4,
1984 ANPP-31312 WFg/KLM
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2 and 3
Docket Nos. STN-50-528/529/530 Shutdown Cooling System Upgrade File:
84-056-026; G.1.01.10
Reference:
Letter to G.W. Knighton, NRC, from E.E.
Van Brunt, Jr.,
- APS, dated October 9, 1984;
Subject:
Shutdown Cooling System Upgrade.
Dear Mr. Knighton:
Attached are additional FSAR changes identified as a result of our revision to the Shutdown Cooling System (SCS) design pressure.
These changes augment the changes identified in the referenced letter.
These changes specifically address the SCS relief valves set pressure (setpoint) to be increased from 435 psig to 467 psig.
If you should have any questions, please contact me.
Very truly your CU~
E. E.
Van Brunt, Jr.
APS Vice President Nuclear Production ANPP Project Director EEVBJr/KLM/no Attachment cc:
E. A. Licitra w/a A. C. Gehr w/a R.
P.
Zimmerman w/a 8412060001.
841204 PDR ADOCK 05000528 A
PDR pW(
TJ
December 4,
1984 ANPP-31312 STATE OF ARIZONA
)
) ss.
COUNTY OF MARICOPA)
I, Edwin E.
Van Brunt, Jr.,
represent that I am Vice President, Nuclear Production of Arizona Public Service
- Company, that the foregoing document has been signed by me on behalf of Arizona Public Service Company with full authority to do so, 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.
Edwin E.
Van Brunt, Jr.
Sworn to before me this
~
day of 1984.
Notary Public Pfy Commission Expires:
My'Cominlssfori Expires April 6, 5887
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INTEGRITY OF REACTOR COOLANT PRESSURE BOUNDARY 5.2.2.7 Material S ecification Refer to CESSAR Section 5.4.13.
In addition, for material specifications related to the secondary system overpressuriza-tion protection refer to section 10.3.2 5.2.2.8 Process Instrumentation'efer to CESSAR Section 5.2.2.7.
In addition, refer to fig-ures 5;l-l and 10;3-1 for the instrumentation related to primary and secondary system overpressurization protection, respectively.
5.2.2.9 S stem Reliabilit Refer to CESSAR Section 5.2.2.8.
Also, refer to sections 5.1.5 and 10.3.2 for a discussion of secondary system overpWessure protection reliability.'.2.2.10 Testin and Ins ection Testing and inspection of primary and secondary valves are governed>>by ASME Section XI.
Testing and inspection of the secondary safety valves is discussed in sections 3.9, 14.2 and 16.3/4.
5.2.2.11 Ove ressure Protection Durin Low Tem erature Conditions Refer to CESSAR Section 5.2.2.10+
/R/5E+7 H++E.
5.2.3 REACTOR COOLANT PRESSURE BOUNDARY MATERIALS 5.2.3.1 Material S ecifications Refer to CESSAR Section,5.2.3.1.
5.2.3.2 Com atibilit with Reactor Coolant
,5.2.3.2.1 Reactor Coolant Chemistry Refer to CESSAR Section 5.2.3.2.1.
February 1984 5,2-23 Amendment 12
INSERT A TO PAGE 5.2-23:
Except as specifically modified by the following changes:
For PVNGS-specific Pressure-Temperature curves refer to the PVNGS Technical Specifications.
CESSAR Figure 5.2-1 is superceded by figure 5.2-7.
CESSAR Figure 5.2-2 is supeceded by figure 5.2-8.
CESSAR Subsection 5.2.2.10.2.3 pertinent valve parameter setpoint is 467 psig.
5 2.7 Figure Palo Verde Units 1,2 and 3
Pressure Transient Resulting From 2
HPSZ and 3 Charging Pumps injecting Aass input to a Water-Solid RCS with Letdown isolated and One SCS Relief Valve Set at 467 psig.
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