ML17304B073
| ML17304B073 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde |
| Issue date: | 03/16/1989 |
| From: | Haynes J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 192-00458-TDS-J, 192-458-TDS-J, 1SR-89-002, 1SR-89-2, NUDOCS 8903230492 | |
| Download: ML17304B073 (8) | |
Text
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D BU'EON DEMONSTRATION SYSTEM REGULA INFORMATION DISTRIBUTIO YSTEM (RIDS)
ACCESSION NBR:8903230492 DOC.DATE: 89/03/16 NOTARIZED: NO DOCKET FACIL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi 05000528 AUTH.NAME AUTHOR AFFILIATION HAYNESgJ.G.
Arizona Nuclear Power Project (formerly Arizona Public Serv RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Special Rept 1-SR-89-002:on 890215,7 day limit exceeded for inoperability of PASS.
DISTRIBUTION CODE:
IE22D COPIES RECEIVED:LTR l
ENCL 1
SIZE:
TITLE: 50.73 Licensee Event Report (LER), Incident Rpt, etc.
NOTES:Standardized plant.
05000528 RECIPIENT ID CODE/NAME PD5 LA CHANgT INTERNAL: ACRS MICHELSON ACRS WYLIE AEOD/DSP/TPAB ARM/DCTS/DAB NRR/DEST/ADE 8H NRR/DEST/CEB 8H NRR/DEST/ICSB 7
NRR/DEST/MTB 9H NRR/DEST/RSB 8E NRR/DLPQ/HFB 10 NRR/DOEA/EAB 11 NRR/DREP/RPB 10 NUDOCS-ABSTRACT RES/DSIR/EIB RGNS FILE 01 EXTERNAL: EG&G WILLIAMSiS H ST LOBBY WARD NRC PDR NSIC MURPHYgG.A NOTES:
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1 RECIPIENT ID CODE/NAME PD5 PD DAVISgM ACRS MOELLER AEOD/DOA AEOD/ROAB/DSP DEDRO NRR/DEST/ADS 7E NRR/DEST/ESB 8D NRR/DEST/MEB 9H NRR/DEST/PSB 8D NRR/DEST/SGB 8D NRR/DLPQ/QAB 10 NRR/DREP/RAB 10
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1 NOTE 'IO ALL"RIDS" RECIPIENIS'IZASE HELP US 'IO REXUCE HASTE!
CDNI'ACr 'IHE DOCUMENI'GNIROL DESK RQCN Pl-37 (EXT. 20079)
KO EIiQ4ZNATE V3UR NAME FRY DISTRIHUTIGN LISTS FOR DOCQQRZS V3U DON'T NEEDt TOTAL NUMBER OF COPIES REQUIRED:
LTTR 47 ENCL 46
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Arizona Nuclear Power Project P.O. BOX 52034
~
PHOENIX. ARIZONA85072-2034 192-00458-TDS/JGH/RJR March 16, 1989 U.
S. Nuclear Regulatory Commission NRC Document Control Desk Washington, D.C.
20555
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 1
Docket No.
STN 50-528 (License No. NPF-41)
,Special Report 1-SR-89-002 File:
89-020-404 Attached please find Special Report 1-SR-89-002 prepared and submitted pursuant to Technical Specifications 3.3.3. 1 ACTION 28(2) and 6,9.2.
This report discusses the inoperability of the Post Accident Sampling System.
If you have any questions, please contact T.
D. Shriver, Compliance
- Manager, at (602) 393-2521.
Very truly yours, JGH/TDS/RJR/kj Attachment cc:
D.
B. Karner E.
E.
Van Brunt, Jr.
J.
B. Martin T. J, Polich M. J.
Davis A.
C, Gehr INPO Records Center J.
G.
Haynes Vice President Nuclear Production (all w/attachments) 8qpppgp492 8 ppp~~8 wp3i6 pDR Agocv, 0 pNU S
If II I
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PALO VERDE NUCLEAR GENERATING TION Post Accident Sampling System Inoperable Greater Than 7 Days License No.
NPF-41 Docket No.
STN 50-528 Special Report No. 1-SR-89-002 This Special Report is being submitted pursuant to Technical Specification 3.3.3. 1 ACTION 28(2) and Technical Specification 6.9.2 to report an event in which the Post Accident Sampling System was inoperable for greater than seven (7) days.
The seven day limit was exceeded at approximately 1055 MST on February 15, 1989.
At approximately 1055 MST on February 8, 1989 the Post Accident Sampling System (PASS) was declared inoperable as a result of a valve (HPA-UV-001) in the Containment Hydrogen Control System (HP) failing its surveillance test.
The valve was subsequently declared operable on February 11, 1989 at approximately 1535 MST.
This information is included as it provides the time of event initiation.
At approximately 1305 MST on February 8, 1989 while sampling the Reactor Coolant System Hot Leg, the sample system depressurized from approximately 2100 PSI to approximately 700 PSI.
Concurrently, an alarm was received on Radiation Monitor RU-9 (Auxiliary Building Lower Levels Ventilation Exhaust).
Immediate action was taken to isolate the sample system.
Isolating the sample system successfully allowed RU-9 to return to its normal range.
Pursuant to Technical Specification 3.3.3. 1 ACTION 28(1) the Preplanned Alternate Sampling Program (PASP) was placed in effect at approximately 1030 MST on February 15, 1989.
Troubleshooting was conducted in accordance with approved work documents and with the assistance of the System Engineer.
This effort identified the following deficiencies:
(1)
Relief Valve PSV-0019 was found to be leaking to atmosphere.
This valve was replaced on February 12, 1989.
(2)
Backpressure Regulator (PCV 19) was found to be leaking to atmosphere.
The valve was replaced on February 21, 1989.
(3)
On February 16, 1989 during performance of a Preventive Maintenance task in accordance with an approved work document, flow switch (FS-2) could not be adjusted as required.
On February 21, 1989 a
new flow switch was installed in the system.
During subsequent
- testing, the switch was found to be incorrect in that the contact action was reversed.
On February 28, 1989 the appropriate switch was installed in the system.
(4)
During testing conducted on February 24,
- 1989, sample valves (SV-4, SV-5, HV-4,and SV-19) were found to be leaking.
These valves were replaced on February 25, 1989.
Speci.al Report 1-SR-89-002
.Page 2
(5)
On Harch 4, 1989, during testing, relief valve (PSV-101) was found to be leaking by its seat.
The valve disc and seat were cleaned, and the leakage ceased.
Investigation indicates that the mostly likely cause of the event which occurred on February 8, 1989 is an overpressurization of the PASS system caused by misoperation of the bypass valve around the pressure reducing element during RCS sampling.
The PASS piping is rated for RCS pressure but the downstream valves are not.
This event is under investigation.
Upon successful completion"of retesting, the Post Accident Sampling System was restored to service at approximately 0841 HST on Narch 8, 1989.
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