ML17298B346
| ML17298B346 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 10/15/1984 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| RTR-REGGD-01.068, RTR-REGGD-1.033, RTR-REGGD-1.068 ANPP-30841-TFQ, NUDOCS 8410170182 | |
| Download: ML17298B346 (10) | |
Text
REGULATOR>
INFORMATION DISTRIBUTION %TEN (RIBS)
ACCESSION NBR:8410170182 DOC ~ DATE: 84/10/15 NOTARIZED:
YES FACIL:STN-50 528 Palo Verde Nuclear Statiani Unit 1F Arizona Publi STN-50-529 Palo Verde Nuclear Stationi Unit 2F Arizona Publi STN-50-530 Palo Verde Nuclear-StationF Unit 3F Arizona Publi AUTHBNAME AUTHOR AFFILIATION VAN BRUNTFE',E.
Arizona Public Service Co ~
REC IP ~ NAME" RECIPIENT AFFILIATION KNIGHTON G
Licensing Branch 3
DOCKET 05000528 05000529 05000530 SUBJECT!
Forwards proposed change. to FSAR Section 1.8 re exception to Reg Guide 1,68 'xception uses guidelines in App B of Reg Guide 1.68<Rev 2, to -have procedures available either 60 days prior to fuel load or 60 days prior to scheduled users DISTRIBUTION CODE!
B001D COPIES RECEIVED!L'TR ENCL SIZE:
TITLE: Licensing Submittal:
PSAR/FSAR Amdts 8 Related Cort espondence NOTES:Standardized
- plant, Standardized plant.
Standardized plant; 05000528 05000529 05000530 RECIPIENT ID CODE/NAME'RR/DL/ADL NRR LB3 LA INTERNAL ADM/LFMB IE FILE IE/DEPER/IRB 35 NRR ROEgM ~ L NRR/DE/CEO 11 NRR/DE/EQB 13 NRR/DE/MEB 18 NRR/DE/SAB 24 NRR/DHFS/HFEB40 NRR/DHFS/PSRB NRR/DSI/AEB 26 NRR/DSI/CPB 10 NRR/DSI/ICSB 16 NRR/DSI/PSB 19 NRR/DSI/RSB 23 RGN5 EXTERNAL: ACRS 41 DMB/DSS (AMDTS)
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Arizona Public Service Company Director of Nuclear Reactor Regulation Attention:
Mr. George Knighton, Chief Licensing Branch No.
3 Division of Licensing U. S. Nuclear Regulatory Commission Mashington, D. C.
20555 October 15, 1984 ANPP-30841 TFQ/JYM
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2 and 3
Docket Nos. STN-50-528/529/530 Exception to R. G. 1.68; procedure availability File: 84-056-026 G.l.01.10
Dear Mr. Knighton:
Attached is a proposed change to Section 1.8 of the FSAR concerning an exception to Regulatory Guide 1.68, as requested by the staff reviewer.
The exception uses the guidelines in Appendix B of Regulatory Guide 1.68 Revision 2, August 1978, in lieu of Revision 0, November,1973, to have procedures available either 60 days prior to fuel load or 60 days prior to their scheduled use.
If you have any questions, please contact me.
Very truly yours EEVBJr/JYM/bg Attachment E. E.
Van Brunt, Jr.
APS Vice President Nuclear Production ANPP Project Director cc:
E. A. Licitra w/a A. C. Gehr w/a D. Becker '/a 8410170182 841015 PDR ADOCK 05000528 A
&DR
V.
s
ANPP-30841 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.
Swore ro before me rhds~day od f
'y Commission. Expires:
t8y Commlsston Expires AoN 6, 1907
, 1984.
Notary Public
I' I
T K
1 1A II
'o Pr t,
PVNGS FSAR CONFORMANCE TO NRC REGUIATORY GUIDES B.
Position C.l of Regulatory Guide 1.67 requires that the magnitude of the reaction force, the anticipated transient behavior, and the basis for their determina-tion should be included in the design specification for the valve.
Since all of the above are characteris-tic to each valve manufacturer, it is not current practice to stipulate these data.
- Rather, the manufac~
turer supplies that information after selection. of the valve, orifice size, inlet and outlet OD, etc., to accommodate the flow rates required by the Design Specification.
This manufacturer supplied information is then used in the design of the relief/safety valve, as discussed in section 3.9.3.3, Design and Installa-tion Criteria, Pressure-Relieving Devices (Open System).
REGULATORY GUIDE 1.68:
Preoperational and Initial Startup Test Programs for Water-Cooled Power Reactors (Revision 0, November 1973)
RESPONSE
The positions and guidelines of Regulatory Guide 1.68 are accepted with the following exceptions and clarifications:
A.
B.
/4~7 g
C.
Power Ascension Tests will be conducted using power plateaus of 20%, 50/, 80/,
and 100/ instead of 25%,
50%,
75%, 100/ as recommended in paragraph D.4 of Appendix A to Regulatory Guide 1.68.
Procedures will be available 60 days prior to their scheduled use instead of 30 days prior to their scheduled use or 90 days prior to fuel load as recommended in paragraph 2 of Appendix B to Regulatory Guide 1.68.
(See section 14.2.11.)
Implementation of Regulatory Guide 1.68 is discussed in section 14.2 and in CESSAR section 1.8.
See CESSAR 14.2.7.1 for additional exceptions and clarifications to Regulatory Guide 1.68.
Amendment 12 1.8-50 February 1984
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