ML17304A286
| ML17304A286 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 07/15/1988 |
| From: | Karner D ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 161-01172-DBK-P, 161-1172-DBK-P, NUDOCS 8807260393 | |
| Download: ML17304A286 (4) | |
Text
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'Wp'l REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8807260393 DOC.DATE: 88/07/15 NOTARIZED: NO DOCKET FACIL:STN-50-529 Palo Verde Nuclear Station, Unit 2, Arizona Publi 05000529 AUTH.NAME AUTHOR AFFILIATION KARNERjD B Arizona Nuclear Power Project (formerly Arizona Public Serv RECXP.NAME RECXPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards summary of results of Unit 2 shutdown outside the control room test.
DISTRIBUTION CODE: IE26D COPIES RECEIVED:LTR Q ENCL g SIZE:
TITLE:'Startup Report/Refueling Report (per Tech Specs)
NOTES:Standardized plant.
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05000529 RECIPIENT ID CODE/NAME PD5 LA LICITRA,E XNTERNAL: ACRS RTON G
02 RGN5 FILE 01 EXTERNAL:. LPDR NSIC NOTES COPIES LTTR ENCL 1
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1 RECIPIENT ID CODE/NAME PD5 PD DAVXS,M ARM TECH ADV NUDOCS-ABSTRACT RES/DSIR DEPY RGN2/DRSS/EPRPB NRC PDR COPIES LTTR ENCL 1
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TOTAL NUMBER OF COPIES REQUIRED; LTTR 22 ENCL 21
Arizona Nuclear Power Project P.O. BOX 52034
~
PHOENIX, ARIZONA85072-2034 161-.01172-DBK/PGN July 15, 1988 Docket No.
STN 50-529 Document Control Desk U.S. Nuclear Regulatory Commission Mail Station Pl-137 Washington, D.C.
20555
Reference:
Letter from J.
G. Haynes (ANPP) to NRC, dated. 3/13i87 (161-00075)
Sub5ect:
Unit 2 Startup Report Supplement 1
Dear Sirs:
Sub5ect:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 2 Shutdown from Outside the Control Room Test File:
88-001-404;t 88-F-056-026 Attached please find a
summary of the results of the Unit 2
Shutdown from Outside the Control Room Test.
This test was originally reported as Section 6.15 of the PVNGS Unit 2 Startup Report and was open at the time the referenced supplement was submitted.
Supplement 1 committed to submitting a summary of. the results upon completion of this test.
If you have any questi'ons or require additional information, please call A. C. Rogers at (602) 371-4041.
Very truly yours,
'D.'R.L~~y D. B. Karner Executive Vice President Pro5ect Director DBK/PGN/pvk Attachment cc:
J.
B. Martin all w/a T. J. Polich G.
W. Knighton M. J. Davis A. C. Gehr INPO Records Center Director, Office of ISE, USNRC 8807260393 880>>>
pDR ADOCK 050005>9 P
ATTACHMENT SHUTDOWN FROM OUTSIDE THE CONTROL ROOM TEST RESULTS (CESSAR SECTION 14.2.12.5.8)
TEST OBJECTIVES AND
SUMMARY
The objective of 73PA-2SF02 "Shutdown Outside Control Room (20% Power) was to demonstrate the reactor can be tripped from outside the Control Room and the plant maintained in hot standby conditions for at least 30 minutes from 'outside the Control
- Room, utilizing only Train B
equipment and the minimum, shift personnel required by Technical Specifications.
The acceptance criterion for this test was to perform a safe shutdown of the plant from outside the control room and maintain selected plant parameters within a specified range for at least 30 minutes using equipment that would normally be available only at the remote shutdown panel.
All. applicable acceptance criteria were met, showing that a safe shutdown could be conducted and the plant stablized in hot standby conditions from outside the control room.
TEST DESCRIPTION The test is performed by utilizing a normal operating crew and a standby crew.
The standby crew serves as control room observers and are to take action only if a problem that involves plant safety develops.
The operating crew consists of the minimum shift complement as defined in Table 6.2-1 of the PVNGS Technical Specifications.
The test was performed on February 20, 1988 while the plant was operating at 20X of rated power.
The operating crew performed the test by evacuating the Control Room and proceeding to the r'emote shutdown panel.
The operating crew initiated and verified the reactor trip from outside the Control Room.
The reactor trip was initiated by an operator at the Reactor Trip Switchgear.
After the trip the operating crew established control of the plant utilizing Train B equipment and the Remote Shutdown Panel.
The plant was maintained in hot standby for 30 minutes by the operating crew.
Control of the plant was then transferred to the standby crew in the Control Room and the Remote Shutdown Panel secured.
SHUTDOWN FROM OUTSIDE THE CONTROL ROOM TEST RESULTS ATTACHMENT Page 2 of 2 TEST RESULTS Below is a
comparison of test acceptance criteria parameters and actual variations observed during the performance of the test.
Acce tance Criteria Observed Values Pressurizer Pressure H
2150 2275 psia 550'F 569'F 2166 2265 psia 566 F 567 F
Pressurizer Level Steam Generator Pressure Steam Generator Level Greater than 26X '0X 36X 1120 - 1220 psia 1162 1176 psia Greater than 35X WR 81 47-75%
As shown by the above parameters and a review of the test data the plant was maintained in a
stable hot standby condition with adequate pressure and temperature control of the RCS and SG's from the Remote Shutdown Panel utilizing Train B equipment.
The test results are adequate to demonstrate conformance to the acceptance criteria provided in Regulatory Guide 1.68.2, Revision 1
and CESSAR Section 14.2.12.5.8.
CONCLUSION This test demonstrated the ability of the minimum shift crew to trip from outside the Control Room and maintain the plant in a stable condition utilizing Train B
components and the Remote Shutdown further verified that the procedure 42AO-2ZZ27 "Abnormal Procedure-Shutdown Outside Control Room" provides adequate guidance of the pIant from the Remote Shutdown Panel.
the reactor hot standby Panel.
It Operating for control