ML17303B113
| ML17303B113 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 05/10/1988 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17303B114 | List: |
| References | |
| NUDOCS 8805190090 | |
| Download: ML17303B113 (5) | |
Text
+gg AEQUI~Wp,
+
0 Cy J
0O I
Og
~O
+>>*+~
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ARIZONA PUBLIC SERVICE COMPANY, ET AL.
DOCKET NO.
STN 50-528 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
32 License No.
NPF-41 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment, dated March 2, 1988, by the Arizona Public Service Company (APS) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, El Paso Electric
- Company, Southern California Edison Company, Public Service Company of New Mexico, Los Angeles Department of Water and Power, and Southern California Public Power Authority (licensees),
complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of Act, and the regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; 0.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, paragraph 2.C of Facility Operating License No.
NPF-41 is hereby amended to include the following additional condition:
BSO5i~<<~
SOOOMe sBO510 PDR ADOCK o PD P
~(13)
RCP Shaft Yibration Monitorin Pro ram Section 5.!.1, SSER 12 APS shall implement an augmented vibration monitoring program for each of the four reactor coolant pumps that includes the following elements:
(a)
(b)
Every four hours, monitor and record vibration data on each of the four reactor coolant pumps.
On a daily basis, perform an evaluation of the pump vibration data obtained in (a) above, by using an appropriately qualified engineering individual.
(c)
When any one vibration monitor indicates a vibration level of Regulatory Commission shall be Emergency Notification System.
any pump exceeds 8 mils due to within four hours the affected continuously monitored and eval individual.
on the reactor coolant pumps 8 mils or greater, the Nuclear notified within four hours via the In addition, when the vibration on a shaft crack or unknown cause, pump shall have its orbit and spectra uated by an appropriately qualified (d)
(e)
When any one vibration monitor on the reactor coolant pumps indicates a vibration level of 10 mils or greater, within one hour, initiate action to place the unit in at least HOT STANDBY within the next six hours, and at least COLD SHUTDOWN-within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
In addition, the affected pump shall be secured after entering HOT STANDBY.
On a daily basis a spectrum analysis shall be performed on the reactor coolant pump shaft vibration data and shall be evaluated for trends by using an individual qualified in that technique.
The evaluation shall consist of comparing the running speed (1xRPM) and twice running speed (2xRPM) spectral components to limits computed from the baseline vibration.
The limits shall be based on the lowest of:
(i) 1.6 times the baseline value, (ii) the mean plus three standard deviations, (iii) 2 mj)s for the 2xRPN component, or (iv) 6 mils for the lxRPM component.
When the amplitude exceeds any limit, further analysis shall be performed.
This analysis shall consist of an inspection of the amplitude versus time plots for a
steadily increasing
- trend, and a review of other plant data which might explain the change in amplitude.
If it is confirmed that the trend is not caused by plant or pump'onditions unrelated to a shaft crack, the trend shall be extrapolated manually and/or by computer to predict the time at which the vibration is expected to reach 10 mils. If the projected time for reaching 10 mils is one week or In the event new limit methods are chosen, the shall be evaluated by the 1/
licensees to assure that the new methods are equal to or better than the above method.
The Commission shall be advised within one week if new methods are chosen.
less, within one hour, initiate action to place the Unit in at least HOT STANDBY within the next six hours and at least COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
In addition, the affected pump shall be secured after entering HOT STANDBY.
The Regional Administrator, Region V may relax or rescind, in writing, any of the above vibration monitoring conditions upon a showing by the licensees of good cause.
3.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Date of Issuance:
Mm'0~ >988 George
. Knighto, Director Project Directorate V
Division of Reactor Projects - III, IV, V and Special Projects
%u