ML17303A971
| ML17303A971 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 03/18/1988 |
| From: | ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | |
| Shared Package | |
| ML17303A969 | List: |
| References | |
| TAC-67519, TAC-67520, TAC-67521, NUDOCS 8803300123 | |
| Download: ML17303A971 (12) | |
Text
ATTACHMENT 1 PALO VERDE NUCLEAR GENERATING STATION, Ul'lIT 1 OPERATIl'lG LICENSE I'lPF-41 This attachment identifies items which must be completed to the NRC staff's satisfaction in accordance with the schedule identified 'be1ow.-
Prior to entering Mode 1 for the first time, APS shall a.
Have completed a review of the surveillance procedures applicable to the change of mode, and determined that the procedures demonstrate the operability of the required systems with respect to all acceptance criteria defined in the Technical Specifications.
b.
Have dispatched written notification to the NRC Regional Administrator, Region Y, that the action defined in (a), above, has been completed for Mode 1.
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ATTACHNENT 1 PALO VERDE NUCLEAR GENERATING STATION, UNIT 2 OPERATING LICENSE NPF-51 This attachment identifies items which must be corn 1
satisfaction in accordance w th th h
wi e schedule identified below.
1.
Pr'or to entering Node l for the first time, APS shall
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Have installed and opegable a Post Accident Sam lin S st meets the provisions of NUREG-0737 (II.B.3).
b.
Have corn leted a r p
eview of the surveillance procedures a
1
-- to the change of mode, and determined that the demonstrate the operability of the re uired s
s t all acc ptanc cr t d f i erma e oned in the Technical Specifications c.
Have dispatched written notification to the NRC Regional Admi Region V, that the action defined in (a) and (b) above has been completed for Node 1 entry.
2.
APS sh all perform compensatory
- measures, corn lete.
operable all elements of the Radiatio s
0 e
a 1 ation YtonltOl ing System in accol danc8 36152 e sc e
u e and commitments presented ln ANPP letters 34129 and
, dated November 29, 1985 and April 15, 1986, respectively 3.
APS shall submit the following information concerning the char in and to the Office of Nuclear Reactor Regulat' commitments presented in ANPP Letters 34127 and 34174, dated egu a
son sn accordance with the sch d
November 29, 1985 and December 5,
1985, respectively:
a.
An evaluation of the effects of gas binding an ope t' pump assuming that the pump has a preexisting crack in the bl'ock.
ing an operating chargin If this postulated condition will lead to a failure of.the pump to deliver the required flow, APS shall also include'w'ith the evaluation a proposed course of action regarding this outcome.
b.
An evaluation and implementation schedule for st ff regarding the long-term solution which considers alternative hardware changes that may be necessary to eliminate the need for venting hydrogen from the suction of the cha e c arging pumps.
4.
APS shall implement the resolution of the design ad
walls in accordance with the commitments provided i ANPP 1
esign a equacy of masonr 1986.
in etter 36301, 5.
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November 2S 1987 ATTACHMENT l PALO VERDE NUCLEAR GENERATING STATION, UNIT 3 OPERATING LICENSE NPF-74 This attachment identifies items that must be completed to the NRC staff's satisfaction in accordance with the schedule identified below.
l.
Prior to entering Yode l for the first time, APS shall:
llg a.
Have completed a review of the surveillance "procedures applicable to the change of mode and determined that the procedures demonstrate the operability of the required systems. with the respect to all acceptance criteria defined in the Technical Specifications.
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b.
Have dispatched written notification to the NRC Regional A'dministrator, Region V, that the action defined in (a), above, has been completed for Hode 1.
2.
The post accident sampling system shall be operable prior to exce'eding
. 5% power.
3.
a.
very four hours, moni.t'or and record vibration data on ach o
he four reactor coolant pumps.
b.
On a dai
- basis, perform an evaluation of the ump vibration data obtai in a above, by using an approp ately qualified engineering i
'vidual.
c.
When any one vibratl monitor on th reactor coolant pumps indicates a vibration el cf' m'
or oreaier, the I"uclear Regulatory Commission sha be ified within four hours.via the Emergency Notification Syste In addition, when the vibratior, on any pump exceeds 8 mils ue a shaft crack or unknown cause, within four hours he affec d purrp shall have its orbit and spectra continuou y monitored an valuated by an appropriately qual ed individual.
d.
Nhen any one
'ation monitor on the reactor lant pumps indicates a
ibration level of 10 mi ls or greater, ithln one hcur, in'ate action to place the unit in at least STANDBY withi he next six hours, and at least COLO SHUTCOk'N wq in the~ ollowira 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
!n addition the affects c pump sha
)/secured after entering 40T ST~NOL'Y.
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a daily basis a spectrum analysis shall be performed on th rea r coolant pump shaft vibration data and shall be eva ted
'or tre s by using an individual qualified in that tec que.
The evaluation a11 consist of comparing the ru'nning sp (1xRPH) and twice running eed (2xRPM) spectral components t imits computed
,~ from the baseline ibration.
The limits shall e based on the
"'"lowest of:
(a) 1.6 es the baseline valv
, (b) the mean plus three standard deviation
)
2 mils fo he 2xRPM component, or= (d) 6 mils for 1xRPM component.
-When t amplitude exceeds any limit, further analysis shall be per e
This analysis shall consist
'f an inspection of the amplitu rsus time plots for a steadily increasing trend, and a revi of oth plant data which miaht explain the change in am
>aude.
If it confirmed that the trend is not caused by plant r pump conditions un lated to a shaft crack,
., the trend shall be trapolated manually andlor computer to "predict the tim t which the vibration is expecte o ~each 10 mils.
1f th rojected time for reaching 10 mils is o
week or less,'it one hour, initiate action to place the Unit at least HOT ST BY within the next six hours and at least COLD. SHUT wit 'he 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 sh secured after entering HOT STANDBY.
The Regional Administrator, Region Y may relax or rescind, in writina,.any of the above vibration monitoring conditions upon a showing by the licensees of good cause.
4.
Within 96 days of the commencement of the Palo Verde Unit 2 irst refueling outaae, the licensee shall submit a report to the NRC concerning the inspection of the Unit 2 reactor coolant
- pumps, This report shall include inspection results, an evaluation of the Unit I and Unit 2 pump shaft dearadation findings and proposed actions to be taken with respect to Unit 3 'continued operation.
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6.
APS shall install modified reactor coolant pump shafts,during the, first re ueling outage which include the modifications described in Figure OES-3 of the attachments to the licensees'ovember 5,
1987 letter.
= In li e ettcr than the a
e aavised within one wee iT new above method.
The en.
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methods are chosen, they.shall he ev to assure that the new
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INSERT APS shall implement an augmented monitoring program for each of the four reactor coolant pumps that includes the following elements:
Each pump will be continuously monitored with at least one shaft proximity vibration transducer with a
control room alarm.
No additional equipment or monitoring is required for the failure of a
single channel.
Should a
channel
- fail, a channel check shall be performed within one hour, to verify the failure of the channel.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the channel
- failure, status of the affected channel shall be reviewed by an appropriately qualified individual.
For the failure of a
vibration monitoring channel, excluding sensor, steps will be taken to correct the failed channel.
If a sensor has failed, it will be repaired/replaced at the next outage of sufficient duration.
When the ability to monitor both channels is lost, monitoring will be restored within 7 days by repair or monitoring with external equipment.
If monitoring capability is not restored within 7 days, wi.thin one hour initiate action to place the unit in at least HOT STANDBY within the next 6
hours.
The affected reactor coolant pump(s)
(RCP) will be secured (unless more than two pumps are affected) except for testing until corrective action is completed which would allow monitoring on at least one channel.
The Nuclear Regulatory Commission shall be
- notified, via the Emergency Notification System within four. hours, of the time capability to monitor all channels is lost and again within four hours of commencement of a plant shutdown, should one be required.
b.
Every four hours, vibration data on each pump will be monitored and recorded.
On a daily basis, an evaluation of the pump vibration data obtained per b.
above will be performed by an appropriately qualified individual.
When actual vibration of any reactor coolant pump reaches a
level of 8
mils or greater the Nuclear Regulatory Commission shall be notified within four hours via the Emergency Notification System.
In addition, when the vibration on any pump exceeds 8
mils or greater due to a
shaft crack or unknown cause, within four hours the affected pump shall have its orbit (if available) and spectrums continuously monitored and evaluated by an appropriately qualified individual. If the vibration is confirmed to be caused by pump conditions other than a
crack or instrumentation malfunctions, appropriate actions commensurate with the cause will be taken per approved plant abnormal operating procedures.
Monitoring shall continue on a frequency determined by an individual appropriately qualified in vibrational analysis until the vibration decreases
'below 8 mils.
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When actual vibration of any reactor coolant pump reaches a
level of 10 mils or greater due to a cracked shaft, or other unknown
- cause, within one hour action shall be initiated to place the unit in at least HOT STANDBY within the
. following six hours.
In
- addition, the affected pump will be secured following entry into Mode 3
(HOT STANDBY) and it will remain secured, except for the purpose of testing, until corrective action has been completed.
On a daily basis, a spectrum analysis shall be performed on the RCP shaft vibration and shall be evaluated for trends by using an individual qualified in that technique.
The evaluation shall consist of comparing the running speed and twice running speed components to limits computed from the baseline vibration.
The current method used is to compute the'lowest of:
i) 1.6 times the baseline value; ii) the mean plus three standard deviations of the
~'I L baseline value; iii) 2 mils for the twice speed component, or iv) 6 mils for the running speed component.
In~the event new limits or methods are
- chosen, prior to their im'plementation they will be evaluated to assure that quality of results'ill be equal to or better than those for the current method The Nuclear Regulatory Commission shall be notified 10 days prior'.to the implementation of a
new spectral analysis method.
When the amplitude exceeds any limit, further analysis shall be performed.
This analysis shall consist of inspecting the amplitude versus time plots for a
steadily increasing trend, and review of other plant data which might explain the change.
If a trend is confirmed to indicate the presence of a shaft
- crack, the trend will be extrapolated to predict the time at which vibration is expected to reach 10 mils.
The unit will be brought to HOT STANDBY and the affected pump will be secured per e.
above at least one week prior to the extrapolated time unless 'the projected time is within a week in which case the unit will be shutdown per e.
above.
The affected reactor coolant pump will remain secured, except for the purpose of
- testing, until corrective action has been completed.
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