ML17299A570
| ML17299A570 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 08/30/1985 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| ANPP-33313-EEVB, NUDOCS 8509050135 | |
| Download: ML17299A570 (17) | |
Text
REGULATORNROffNATION DISTRIBUTION +TEN (RIDS)
N, ACCESSION NBR:8509050135 DOC ~ DATE: 85/08/30 NOTARIZED:
YES DOCKET FACIL:STN"50-529 Palo Verde Nuclear Stationi Unit 2i Arizona Publi 05000S29 STN-50-530 Palo Verde Nuclear Stationi Unit 3i Arizona Publi 05000530 AUTH BYNAME AUTHOR AFFILIATION VAN BRUNTEE ~ E ~
Arizona Nuclear Power Project (former ly Ar izona Public Serv RECIP, NAME RECIPIENT AFFILIATION KNIGHTON z G ~ I'I ~
Licensing Branch 3
S UBJECT:
Forwards changes to FSAR Sections 11 '.2.lr10.4.4.2r 3B8,1.2.2 II, 9.5.4.4ireflecting correction of closure time listed for turbine bypass valves L applicable code for containment bldg design.
DISTRIBUTION CODE:
B001D COPIES RECEIVED:LTR J ENCL SIZE:
TITLE: Licensing Submittal:
PSAR/FSAR Amdts 8, Related Correspondenc~
NOTES:Standardized plant.
Standardized plant ~
05000529 05000530 RECIPIENT ID CODE/NAME NRR/DL/ADL NRR LB3 LA INTERNAL: ACRS ELD/HDS3 IE/DEPER/EPB 36 NRR ROEiM ~ L NRR/DE/CEB 11 NRR/DE/EQB 13 NRR/DE/MEB 18 NRR/DE/SAB 24 NRR/DHFS/HFEBIIO NRR/DIIFS/PSRB NRR/DSI/AEB 26 NRR/DSI/CPB 10 NRR/DSI/ICSB 16 NRR/DS I/PSB 19 NRR/DS I/RSB 23 RGNS EXTERNAL; 2QX DMB/DSS (AMDTS)
NRC PDR 02 PNL GRUELrR COPIES LTTR ENCL 1
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1 2
2 1
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1 1
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3 3
1 1
1 1
1 1
1 RECIPIENT ID CODE/NAh1E NRR LB3 BC LICITRAg E 01 ADM/LFMB IE FILE IE/DQAYT/QAB21 NRR/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/DSI/ASB NRR/DS I/CSB 09 NRR/DS I/METB 12 N
/RAB 22 0Q RM AMI/MIB BNL(AMD'TS ONLY)
LPDR 03 NSIC 05 COPIES LTTR ENCL 1
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TOTAL hIUMBER OF COPIES REQUIRED:
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Arizona Nuclear Power Project P.o. BOX 52034 4
PHOENIX, ARIZONA85072-2034 Director of Nuclear Reactor Regulation Attention:
Mr. George W. Knighton, Chief Licensing Branch 3 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D. C.
20555 August 30, 1985 ANPP-33313-EEVB/JKO
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 2 and 3
Change to PVNGS FSAR (Chapters 3, 9, 10, and ll)
Docket Nos. STN-50-529/530 File:
85-056-026 G.l.01.10
Dear Mr. Knighton:
Attached for your review on PVNGS Units 2 and 3 are FSAR changes to sections 11.3.2.1, 10.4.4.2, 3.8.1.2.2, and 9.5.4.4.
These changes involve:
(1) revising the FSAR to show that the waste gas compressors stop filling the waste gas decay tanks when the surge tank pressure reaches 1.5 psig which corresponds to a pressure of 0.5 psig at the suction side of the compressors; (2) correcting the closure time listed for the turbine bypass valves; (3) correcting the FSAR to reflect the applicable code for the design of the containment building; (4) clarifying that the diesel fuel oil storage tank capacity versus inventory is a 14-day total plus a 15X margin to preclude an error in interpretation that the tanks must be maintained 100X full.
Me believe these changes are justified because:
(1) the pressure setpoint for the low pressure switch was changed to 1.5 psig due to a change to the physical location of this pressure sensor and this ensures that the suction pressure for the compressor will not be below 0.5 psig; (2) correcting the closure time for the turbine bypass valves aligns the FSAR with CESSAR, and system "analysis and NSSS plant licensing are based on the requirements of CESSAR; (3) the wrong c'ode was referenced in the FSAR and needed correcting to apply to containment
- design, not construction; (4) the Standard Review Plan, PVNGS SER and the Technical Specifications are all based on a 7 day inventory for both diesel generators rather than the total capacity of the tanks as being required for diesel generator operation.
For PVNGS Unit 1, safety reviews and evaluations have been completed for implementation of these changes in accordance with the requirements of 10CFR 50.59.
The safety reviews and evaluations have determined that there are no unreviewed safety questions involved with the changes.
These changes will be included in the next FSAR update.
8509050<~5 05O00529 PDR gQOCK PDR g0
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G. M.'nighton
.Change to PVNGS FSAR (Chaa 3, 9, 10, and 11)
ANPP-33313 Page 2
If you have any questions concerning these
- changes, please contact M. F. Quinn of my staff.
Very truly yours, P-P.VcLLI E. E.
Van Brunt, Jr.
Executive Vice President Project Director EEVB/JKO/slh Attachment cc:
E. A. Licitra M. C. Ley R. P.
Zimmerman A. C. Gehr
0'
STATE OF ARIZONA
)
) st COUNTY OF MARICOPA)
I, Edwin E.
Van Brunt, Jr.,
represent that I am Executive Vice President, Arizona Nuclear Power Project, 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 thie~QQ day of
, 1985.
1 /
My Commission Expires:
My Commission Expires April 6, 1987 Notary Public
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.Change tn PVNGS PSAR (Cha 3, 9, 10, and ll)
" ANPP-33313 Page 3
bcc:
D. B. Karner J.
G. Haynes R.
M. Butler W. E. Ide E. C. Sterling A. C. Rogers W. F. Quinn T.'. Quan LCTS Coordinator K.
W. Gross J.
M. Allen J.
R.
Bynum J. Orlowski L. G. Papworth A. J.
McCabe J.
D. Houchen S. Shapiro C. F. Ferguson SARCN Nos.:
- 2026, 2042,
- 2044, 2045
PVNGS FSAR GASEOUS NASTE MANAGEMENT SYSTEMS Sources for the GRS include the gases from:
~
Reactor drain tank Volume control tank
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Refueling failed fuel detectors
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Gas stripper
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Reactor vessel vent The high-activity gases accumulate in the waste gas surge tank and are compressed and stored in the waste gas decay tanks.
Mhen the surge tank pressure reaches 3 psig, the compressor selected for operation starts automatically and starts charging the online decay tank. If the surge tank pressure reaches 3.5 psig the standby compressor will automatically start.
Operation of either compressor automatically stops when the IKSQ,Rl surge tank pressure decreases to~0.5 psig.
When decay tank pressure reaches 350 psig, an alarm is actuated, and compressor operation. is terminated manually.
Identical compressors are provided to minimize system down time.
Each decay tank is sampled prior to discharge.
No special
'ixing is considered necessary for the gas.
Each sample is -=
analyzed for radioactivity and the concentration,
- volume, and total radioactivity are recorded.
Isotopic content, of the waste gases is determined and recorded as specified in the station manual procedures.
The maximum rates and quantities of radionuclides released from the gaseous waste decay tanks will be in accordance with the limits imposed by the Plant Technical Specifications.
The rate of release from the decay tanks into the ventilation exhaust, is limited so as not to exceed the release limits of 10CFR20.
Releases are conducted to meet the "as low as is reasonably achievable" objectives of 10CPR50 Append'ix I.
pS'y Corrcsp ccL' ohio c
C ~pro<>or Sock'
[I C55oro op Amendment 14 February 1985
PVNGS FSAR OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM Six of these valves direct steam to the condenser and the "
remaining two vent directly to the atmosphere.
The valves are designed to fully open within 1 second and gulf.
or to modulate full open or closed in a minimum of 15 seconds farl and a maximum of 20 seconds.
The valves are equipped with 5 seegP remote-.operated handwheels to permit manual operation at the valve location.
The two valves which exhaust to the atmosphere are the last to open and the first to close during load rejections, thus minimizing the quantity of steam discharged to the environment.
The valves and piping for the system are located in the turbine building.
The valves in the turbine bypass system are designed to fail closed to prevent uncontrolled bypass of steam.
Should the bypass valves fail to open on command, the main steam safety valves provide main steam line overpressure protection, and the power-operated atmospheric dump valves provide a means for controlled cooldown of the reactor.
The main steam safety valves and power operated atmospheric dump valves are described in section 10.3.2,2.
In the event of a turbine trip, the amounts of radioactivity released and the resultant off-site doses are those stated in section 15.2.
The main steam safety valves.and power-operated atmospheric dump valves are used to control the load transient, if the bypass valves are disabled.
Because the ASME Code safety valves provide the ultimate overpressure protection for the steam generators, the turbine bypass system is defined as a control system and is designed without consideration for the special requirements applicable to protection sy'stems.
Failure of this system will have no detrimental effects on the reactor coolant system.
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PViiIGS FSAR DESIGN OF CATEGORY I STRUCTURES 3.8.1.2 AvoZ5.cable Codes, St ndards, and Specific tions "-
The following codes, standards, regulations, specifications, design criie ia, and NRC Regulatory Guid. s constitute the basis fo" the design, fabrication, cons ruction, testing, avd inservice inspeciion of th covtainment siructures.
t1odifica-tions io thes
- codes, standards, etc.
are made when necessary to meet the specific requirements. of the structure.
These mod'f'cations are indicated iv ihe seciions where references to the codes and siandards ar made.
Later edit'ons of certain base ine standards as noted 'n subseauent sections are acceptable provid'ng they are identified in appli'cable design calculations or speci ications for fabrication, construction, t sting, or insp " ion.
3.8.1.2.1 Regulat'ons The followivg regulaiions apply to contairpent design; Code of Federal Regulations, Title 10-Atomic Energy, Pari 50, Domesiic Lic nsing or Production and Utili-zation Facilit'es, 1972 Code of Federal Regulations, T'tie 29-Labor,
- Part, 1910, Occupat'onal Safety and Health Standards, 1972 3.8.1.2 '
Codes and Standard Specifications The following codes and standards are applicable to contain-ment design.
geih forceJ American Concrete Institute, Building Code Require-ments for Concrete (ACI~).
3 is-7l In the containment design, portions of this code, particularly chapters 18, 19, and Appendix A, are superseded by the other provisions described in section 3.8.1.
American Institute for Steel Construction (AISC)
Specification for the Design, Fabrication and Erection of Structural Steel for Buildings, adopted February 12, 1969 and Supplements No.
1, 2,
and 3, or later edition.
Amendment 12 3.8-8 Februarv 1984 ""
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PVNGS FSAR OTHER AUXILIARYSYST NS transfer pump from a switch in the main control room.
If the transfer pump still fails to operate, a low level day tank alarm is actuated to alert the operator to take corrective action.
Fuel can then be supplied from the redundant train by opening valves on an interconnecting line and the diesel generator may be allowed to continue running.
The automatic pump in the system also may be actuated manually by the operator from the control room or from the diesel gen-erator room local control panel.
9.5.4.4
. Safet Evaluation Safety evaluations are numbered to correspond to the safety design bases and include the following:
A.
Safety Evaluation One The capacity of each of the underground diesel genera-tor fuel oil storage tanks is sufficient for 7-day operation plus a
15% margin of each of the diesel generators using ASTN D-975 diesel fuel oil, having 28API gravity, high heating value of 19,350 Btu/lb, and a low heating value of 18,190 Btu/lb, at the largest actual operating load indicated in section 8.3.
Cross connect lines with double locked closed valves are provided so that either transfer pump can discharge to the fuel oil day tank serving the redundant diesel generator.
The cross connect piping and valves are designed as Seismic Category I.
- Thus, a 14-day total Ca
~
plus a
15% margin diesel fuel oil is avail-able for operation of one diesel generator during a complete loss of offsite electrical power.
Within this period, additional fuel can be delivered to the plant site by truck, rails, or helicopter.
9.5-59
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