ML20080C493: Difference between revisions
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( | TEST RESULTS REPORT - | ||
TEST RESULTS REPORT - | PROCEDDRE NO. | ||
PROCEDDRE NO. 92HF-ISV01 PROCEDURE TITLE Loose Parts and Vibration Monitoring System Hot Functional | 92HF-ISV01 PROCEDURE TITLE Loose Parts and Vibration Monitoring System Hot Functional | ||
/6/83 0 | |||
DATES OF TEST PERFORMANCE | DATE REVISION AT THE COMMENCEMENT OF TESTING DATE 6/7/83 O | ||
REV1!) ION AT C0F1LETION OF TESTING 7 | |||
PREPARED BY: | _ DATE 6/1/83 LATEST TEST CHANGE NOTICE NO. | ||
DATES OF TEST PERFORMANCE 5/6/83 to 6/7/83 PAGE 1 0F 4 C | |||
Review and Approval of Tes t Results d/ | |||
DATE: | |||
PREPARED BY: | |||
./ - | |||
8[/f!d-J p | |||
DM/ | |||
DATE: | |||
TECHNICAL REVIEW: | |||
A /f!ff3 p,,,; N | |||
, DATE: | |||
GROUP SUPERVISOR REVIER: | GROUP SUPERVISOR REVIER: | ||
j' | |||
/ | |||
\\ | |||
DATE: | DATE: | ||
TEST WORKING GROUP MEETING NUMBEE: | TEST WORKING GROUP MEETING NUMBEE: | ||
| Line 43: | Line 52: | ||
DATE: | DATE: | ||
STARTUP 1ANAGER APPROVAL: | STARTUP 1ANAGER APPROVAL: | ||
if -E2 E | if -E2 E 8402080116 831116 PDR FOIA PDR GARDE 03-609 | ||
Test Results Report 92HF-lSV01 | Test Results Report | ||
'6f 92HF-lSV01 | |||
\\ | |||
Page 2. of 4 Test Purpose and Scope | Rev.0 TCN7 Page 2. of 4 Test Purpose and Scope i | ||
The purpose of this test was to obtain baseline data for each reactor coolant pump initial start gnd run during the reactor coolant heatup phase. A second purpose was to botain baseline data for all Loose Parts and Vibration channels during steady state indhich four (4) reactor coolant pumps running and primary parameters of normal operating temperature and pressure. Exception to the data baseline are the six (6) core internal channels because cf no neutron source. | The purpose of this test was to obtain baseline data for each reactor coolant pump initial start gnd run during the reactor coolant heatup phase. A second purpose was to botain baseline data for all Loose Parts and Vibration channels during steady state indhich four (4) reactor coolant pumps running and primary parameters of normal operating temperature and pressure. Exception to the data baseline are the six (6) core internal channels because cf no neutron source. | ||
Complimentary Test None Test Description The data was obtained by two (2) methods: | Complimentary Test None Test Description The data was obtained by two (2) methods: | ||
: 1. The two (2) installed system tape recorders were utilized to record a minimium of five (5) minutes of data. Specific channels associated with each reactor coolant pump were recorded during initial start and run. | : 1. The two (2) installed system tape recorders were utilized to record a minimium of five (5) minutes of data. | ||
Specific channels associated with each reactor coolant pump were recorded during initial start and run. | |||
~ | |||
Each channel was recordeo with four (4) reactor coolant pumps operating at normal plant temperature and pressure. | Each channel was recordeo with four (4) reactor coolant pumps operating at normal plant temperature and pressure. | ||
: 2. A spectrum analyzer and X-Y plotter were used to obtain permanent frequency verses amplitude for a specific point during initial reactor coolant pump run. Each channel. was recorded with the four (4) reactor coolant pumps operating at normal plant temperature and pressure. | : 2. A spectrum analyzer and X-Y plotter were used to obtain permanent frequency verses amplitude for a specific point during initial reactor coolant pump run. | ||
Each channel. was recorded with the four (4) reactor coolant pumps l | |||
The data recording started on May17,1983 and concluded June 7, 1983. During this | operating at normal plant temperature and pressure. | ||
Test Events The data recording started on May17,1983 and concluded June 7, 1983. During this l | |||
time period there were two (2) major problems but neither impacted the data j | |||
gathering. | |||
The first problem symptoms were: No audio output, No -15 volts Reactor Coolant Pump Proximity circuits having identical characteristics. | The first problem symptoms were: No audio output, No -15 volts Reactor Coolant Pump Proximity circuits having identical characteristics. | ||
The cause of this problem appeared to be the proximity probe signal lead being l | The cause of this problem appeared to be the proximity probe signal lead being l | ||
grounded by the metal ID tag installed at the transmitter. Moving the ID tag | grounded by the metal ID tag installed at the transmitter. Moving the ID tag | ||
(, | (, | ||
c1 cared the ground, resetting the -15 volt power supply restored the audio and the proximity circuits again had there individual characteristics. | |||
I l | I l | ||
l | l | ||
Test Results Report 92HF-1SV01 | Test Results Report | ||
{ | |||
Rev.0 TCN 7 page 3 of 4 The second problem symptom was the OK lamp for channel twenty four (24) being intermittenly extinguished. Ea' ch proximity circuit' has an OK status lamp which is illuminated When the circuit is operating. A work order has been written to investigate and repair the problem. | 92HF-1SV01 Rev.0 TCN 7 page 3 of 4 The second problem symptom was the OK lamp for channel twenty four (24) being intermittenly extinguished. | ||
Since the probe and transmitter cre located inside the reactor coolant pump coupling housing, .no investigative work can be initiated presently. | Ea' ch proximity circuit' has an OK status lamp which is illuminated When the circuit is operating. A work order has been written to investigate and repair the problem. | ||
Since the probe and transmitter cre located inside the reactor coolant pump coupling housing,.no investigative work can be initiated presently. | |||
Ncither problem prevented the recording of a11~. required data points. | Ncither problem prevented the recording of a11~. required data points. | ||
There was a total of seven (7) TCN's written of which one (1) was a scope change. | There was a total of seven (7) TCN's written of which one (1) was a scope change. | ||
The scope change was required because the upper chassis tape recorder is hard wired for specific channels dependent upon the X-Y slector switch. | The scope change was required because the upper chassis tape recorder is hard wired for specific channels dependent upon the X-Y slector switch. | ||
The remaining six (6) TCN's corrected typographical errors... revised revision numbers, added new step for alternate test equipment and changed taperecorder drive speed for improved resoluticn. | The remaining six (6) TCN's corrected typographical errors... revised revision numbers, added new step for alternate test equipment and changed taperecorder drive speed for improved resoluticn. | ||
{ | { | ||
Test Results All data points required to be recorded by tape recorder and X-Y plots were made. | |||
There were three (3) TER's written due to the reactor coolant pumps being started prior to the fif teen (15) second elapsed time run of the tape recorder. Two (2) of the recordings had no pre pump start elapse time and one (1) had only ten (10) seconds. | There were three (3) TER's written due to the reactor coolant pumps being started prior to the fif teen (15) second elapsed time run of the tape recorder. Two (2) of the recordings had no pre pump start elapse time and one (1) had only ten (10) seconds. | ||
1 | Conclusion 1 | ||
The data has been obtained and is available in both hard and sof t copy for the. | |||
Reactor Coolant System. This data is a baseline for single pump run from ambient I | Reactor Coolant System. This data is a baseline for single pump run from ambient I | ||
temperature and pressure thru four (4) pump running at standard operating temperature | temperature and pressure thru four (4) pump running at standard operating temperature and pressure with no reactor core, i | ||
Recommendation | |||
: 1. No additional data for this system configuration, l | |||
: 1. No additional data for this system configuration, | |||
: 2. During post core hot functional testing a similiar test should be performed to obtain a new baseline. This would be representitive of the system for the Eddition of the reactor core. | : 2. During post core hot functional testing a similiar test should be performed to obtain a new baseline. This would be representitive of the system for the Eddition of the reactor core. | ||
: 3. During the power ascension time period initial baseline data should be taken | : 3. During the power ascension time period initial baseline data should be taken L-for the six (6) core internal channels when a neutron source is available. | ||
1 e-- | |||
1 | |||
Test Results Report 92HF-ISV01 | Test Results Report 92HF-ISV01 | ||
' g{ -. | |||
Rev.0 TCN 7 Page 4 of 4 | |||
: 4. The acceptance of this test and recorded data is recomended.. The basis for the acceptance recomendation is based on toeeting the required comitment of 'the FSAR Appendix 4A NRC Question 492.1 Responsa 3 by the baseline data bsing recorded on both tape recordings and X-Y iplots for all required channels. | : 4. The acceptance of this test and recorded data is recomended.. The basis for the acceptance recomendation is based on toeeting the required comitment of 'the FSAR Appendix 4A NRC Question 492.1 Responsa 3 by the baseline data bsing recorded on both tape recordings and X-Y iplots for all required channels. | ||
1 1 | 1 1 | ||
l l | l l | ||
i l | I i | ||
i 1 | l i L 1 | ||
o wg-,}} | |||
wg-,}} | |||
Latest revision as of 22:27, 14 December 2024
| ML20080C493 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde, 05000000 |
| Issue date: | 06/14/1983 |
| From: | Colleen Schmidt AFFILIATION NOT ASSIGNED |
| To: | |
| Shared Package | |
| ML20080C249 | List: |
| References | |
| FOIA-83-609 92HF-1SV01, 92HF-1SV01-R00, 92HF-1SV1, 92HF-1SV1-R, NUDOCS 8402080116 | |
| Download: ML20080C493 (4) | |
Text
,.
f x
(
TEST RESULTS REPORT -
PROCEDDRE NO.
92HF-ISV01 PROCEDURE TITLE Loose Parts and Vibration Monitoring System Hot Functional
/6/83 0
DATE REVISION AT THE COMMENCEMENT OF TESTING DATE 6/7/83 O
REV1!) ION AT C0F1LETION OF TESTING 7
_ DATE 6/1/83 LATEST TEST CHANGE NOTICE NO.
DATES OF TEST PERFORMANCE 5/6/83 to 6/7/83 PAGE 1 0F 4 C
Review and Approval of Tes t Results d/
DATE:
PREPARED BY:
./ -
8[/f!d-J p
DM/
DATE:
TECHNICAL REVIEW:
A /f!ff3 p,,,; N
, DATE:
GROUP SUPERVISOR REVIER:
j'
/
\\
DATE:
TEST WORKING GROUP MEETING NUMBEE:
DATE:
PLANT REVIEW BOARD MEETING NUMBER:
DATE:
QUALITY ASSURANCE REVIEW: -
(Required for Test Results Reports not reviewed of IWG)
DATE:
STARTUP 1ANAGER APPROVAL:
if -E2 E 8402080116 831116 PDR FOIA PDR GARDE 03-609
Test Results Report
'6f 92HF-lSV01
\\
Rev.0 TCN7 Page 2. of 4 Test Purpose and Scope i
The purpose of this test was to obtain baseline data for each reactor coolant pump initial start gnd run during the reactor coolant heatup phase. A second purpose was to botain baseline data for all Loose Parts and Vibration channels during steady state indhich four (4) reactor coolant pumps running and primary parameters of normal operating temperature and pressure. Exception to the data baseline are the six (6) core internal channels because cf no neutron source.
Complimentary Test None Test Description The data was obtained by two (2) methods:
- 1. The two (2) installed system tape recorders were utilized to record a minimium of five (5) minutes of data.
Specific channels associated with each reactor coolant pump were recorded during initial start and run.
~
Each channel was recordeo with four (4) reactor coolant pumps operating at normal plant temperature and pressure.
- 2. A spectrum analyzer and X-Y plotter were used to obtain permanent frequency verses amplitude for a specific point during initial reactor coolant pump run.
Each channel. was recorded with the four (4) reactor coolant pumps l
operating at normal plant temperature and pressure.
Test Events The data recording started on May17,1983 and concluded June 7, 1983. During this l
time period there were two (2) major problems but neither impacted the data j
gathering.
The first problem symptoms were: No audio output, No -15 volts Reactor Coolant Pump Proximity circuits having identical characteristics.
The cause of this problem appeared to be the proximity probe signal lead being l
grounded by the metal ID tag installed at the transmitter. Moving the ID tag
(,
c1 cared the ground, resetting the -15 volt power supply restored the audio and the proximity circuits again had there individual characteristics.
I l
l
Test Results Report
{
92HF-1SV01 Rev.0 TCN 7 page 3 of 4 The second problem symptom was the OK lamp for channel twenty four (24) being intermittenly extinguished.
Ea' ch proximity circuit' has an OK status lamp which is illuminated When the circuit is operating. A work order has been written to investigate and repair the problem.
Since the probe and transmitter cre located inside the reactor coolant pump coupling housing,.no investigative work can be initiated presently.
Ncither problem prevented the recording of a11~. required data points.
There was a total of seven (7) TCN's written of which one (1) was a scope change.
The scope change was required because the upper chassis tape recorder is hard wired for specific channels dependent upon the X-Y slector switch.
The remaining six (6) TCN's corrected typographical errors... revised revision numbers, added new step for alternate test equipment and changed taperecorder drive speed for improved resoluticn.
{
Test Results All data points required to be recorded by tape recorder and X-Y plots were made.
There were three (3) TER's written due to the reactor coolant pumps being started prior to the fif teen (15) second elapsed time run of the tape recorder. Two (2) of the recordings had no pre pump start elapse time and one (1) had only ten (10) seconds.
Conclusion 1
The data has been obtained and is available in both hard and sof t copy for the.
Reactor Coolant System. This data is a baseline for single pump run from ambient I
temperature and pressure thru four (4) pump running at standard operating temperature and pressure with no reactor core, i
Recommendation
- 1. No additional data for this system configuration, l
- 2. During post core hot functional testing a similiar test should be performed to obtain a new baseline. This would be representitive of the system for the Eddition of the reactor core.
- 3. During the power ascension time period initial baseline data should be taken L-for the six (6) core internal channels when a neutron source is available.
1 e--
Test Results Report 92HF-ISV01
' g{ -.
Rev.0 TCN 7 Page 4 of 4
- 4. The acceptance of this test and recorded data is recomended.. The basis for the acceptance recomendation is based on toeeting the required comitment of 'the FSAR Appendix 4A NRC Question 492.1 Responsa 3 by the baseline data bsing recorded on both tape recordings and X-Y iplots for all required channels.
1 1
l l
I i
l i L 1
o wg-,