ML17300A712
| ML17300A712 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde |
| Issue date: | 03/20/1987 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 161-00092-EEVB, 161-92-EEVB, NUDOCS 8703300462 | |
| Download: ML17300A712 (8) | |
Text
REGULATORNFORNATION DISTRIBUTION:-
TEll. (RIDSl ACC<
ION NBR: 8703300462 DOC. DATE: 87/03/20 NOTAR ZED:
NO DOCKET FCC IL:STN-50-530 Palo Verde Nuclear Station>
Unit 3I Arizona Pub 1 i 05000530 AUTH. N'AME AUTHOR AFF1LIATIGN VAN BRUNTI E. E.
Arizona Nuclear Pouer Prospect
( former lg Arizona Pub 1 ic Serv RECIP. NAME RECIPIENT AFFILIATION Document Control Branch
<Document Control Desk)
SUBJECT:
RO: on 861104I MSIV SQE-UV-1709 openedi causing cooldown of RCS. Valve closed 5 plant stabilized. Occurrence could no~.
be duplicated. No problems w/valve identified. Removal of fast open circuitrg after installation of valves verified.
DISTRIBUTION CODE:
B021D COPIES RECEiVED: LTR J ENCL 0 SIZF:
TITLE: QR/Licensing Submittal:
Combined Qeneral Distribution NOTES: Standardized plant. M. Davisi NHR: 1Cg.
05000530 RECIPIENT ID CODE/NAME PWR-B ADTS PIJR-B PE ICSB PIJR-B PD7 LA LICITRA>E PWR-B RSB COPIES LTTR ENCL 2
1 1
REC IPlENT ID CODE/NAME Pla'R-B EB PWR-B FOB PliR-B PD7 PD PliR-B PEICSB COPIES LTTR ENCL-INTERNAL: ACRS NRR BMR ADTS NRR PMR-B ADTS EQ ILE 01 EXTERNAL: LPDR NSIC NOTES:
8 1
1 1
ADM/LFMB NRR PNR-A *DTS NRR/DSRO DIR QQC/HDS1 RMI/DDAMI/MIB NRC PDR PNL QRUELIR 0
TOTAL NUMBER OF COPIES REQUIRED:
LT1R 32 ENCL
Qt K
II
8703300462 870320 PDR
~A'OCK 05000530 Arizona Nuclear Power Project
). BOX 52034
~
PHOENIX. ARIZONA85072-2034 March 20, 1987.
161-00092-. EEVB/BJA U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D.C. 20555
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2 and 3
Docket Nos.
STN 50-'528-(License No. NPF-41)
STN 50-529 (License No. NPF-51)
STN 50-530 Corrective Actions for Inadvertent MSIV'pening and Unit 2 Inverter Problems File: 87-A-056-026
Dear Sir:
At 19:35 on November 4,
- 1986, during Precore Hot Functional Testing on PVNGS Unit 3, Main Steam Isolation Valve (MSIV) SGE-UV-170 opened, which caused a cool-down of the reactor coolant system.
The,.valve was subsequently closed by the secondary operator and the plant was stabilized and returned to normal pressure and temperature.
No adverse effects were experienced as a result of the cooldown.
While all indications were those indicative of an MSIV opening in the "fast open"
- mode, the occurrence could not be duplicated, nor did subsequent troubleshooting reveal any problems with the valve, its power supply or normal operating environ-ment.
The following items were performed during troubleshooting:
1.
The fast open circuitry was verified to have been removed following instal-lation of the valves.
2.
All wiring for SGE-UV-170 was verified to be "per design".
3.
Proper operation of SGE-UV-170 and associated solenoid valves was verified twice by stroking the MSIV using the "slow mode".
4.
Proper DC voltages were verified using a strip chart recorder in the auxil'-
iary relay cabinet.
DC valves, powered from the same
- bus, were stroked to ensure that no pertur-bations in MSIV logic power were caused by the valve operators.
0 4
~ '
U.S. Nuclear Regulatory Commission Attention: Document Control Desk
Subject:
Corrective Actions for Inadvertent MSIV Opening and Unit 2 Inverter Problems 161- 00092 Page 2
6.
The "A" train battery charger was de-energized and re-energized to ensure that no, perturbations in MSIV l'ogic power were caused by the chargers.
7.
Operations and Security radios were operated inside the MSIV logic circui-try cabinet at distances of one foot and five feet from the cabinet with no adverse'ffect on MSIV circuitry.
8.
Mechanical vibrations of the cabinet were "simulated" with no adverse effect on the MSIV circuitry.
PVNGS Operations Engineering has reviewed the results of the troubleshooting effort and other related testing and concludes that the event of November 4,
1986 was an isolated incident which could not be duplicated and has no impact on the ability of the valve to perform its design function.
As requested by Region V, the previous testing in items 3, 4, 5
and 6 will be performed again during the Post-Core Hot Functional Testing.
Any exceptions will be documented and justified.
The justifications will.be reviewed by the Plant Review Board.
In addition, these valves will be periodically tested to comply with the ASME Section XI program which insures, that all MSIVs meet their Technical Specification stroke time requirements.
Therefore, it is the position of PVNGS that this event does not present a constraint to the progress towards fuel loading and power ascension.
Unit 2 Inverter Problem; A "fix" for the inverters has been identified and tested in Unit 2.
This fix will be implemented in Unit 3 prior to fuel load.
Other enhancements to the inverters are currently being evaluated.
Very truly yours, E. E.
Van Brunt, Jr.
Executive Vice President Project Director
-EEVB/BJA/rw
Qi
U.S. Nuclear Regulatory Commission Attention:
Document Control Desk
Subject:
Corrective Actions for inadvertent MSXV Opening and Unit 2 Xnverter Problems 161-00092 page 3
ccrc 0.. M.
J.. B.
G.
W.
R.
P.
A. C.
De Michele Martin Knighton Zimmerman Gehr
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