ML20133K698
| ML20133K698 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 10/16/1985 |
| From: | Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| GL-83-28, NUDOCS 8510220251 | |
| Download: ML20133K698 (6) | |
Text
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PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 PHILADELPHIA, PA.19101
$HIELDS L. DALTROFF na77.*U.UOU*"
October 16, 1985 Docket Nos. 50-277 50-278 Mr. John F.
Stolz, Chief Operating Reactors Branch #4 Division of Licensing U.S.
Nuclear Regulatory Commission Washington, D.C.
20555
SUBJECT:
Peach Bottom Atomic Power Station, Units 2 and 3 Generic Letter 83-28, Item 1.2 Post-Trip Review -
Data and Information Capability
REFERENCE:
(1)
- Letter, J.
F. Stolz, USNRC, to E. G.
Bauer, Jr.,
PECo, July 10, 1985 (2)
- Letter, S.
L. Daltroff,.PECo, to J. F.
Stolz, USNRC, November 4, 1983
Dear Mr. Stolz:
The reference (1) letter forwarded the NRC assessment of the completeness and adequacy of our responses to Item 1.2 of the subject Generic Letter for Peach Bottom Units 2 and 3.
Philadelphia Electric Company (PECo), via telecon dated October 11, 1985 between W. C. Birely, PECo, and Mr. G.
E. Gears, USNRC, reque sted an extension to October 16, 1985 for submitting the PCOw response to NRC concerns identified in the reference (1) letter.
This extension was found acceptable by Mr. Gears.
The results of the NRC review are restated below along with our response.
It should be noted that, although it is believed that adequate post-trip review capability presently exists at Peach Bottom, PECo will incorporate many of the " good practices" recommendations identified in Generic Letter 83-28, Item 1.2, into the program currently-in progress to upgrade the process computer for Peach Bottom Units 2 and 3 as discussed in this letter.
/h 851022025185g6 DR ADOCK O 27 09 p
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Mr. John F. Stolz October 16, 1985 f
Page 2 4
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1)
NRC Noted Deviation o
I The " post-trip log" for Peach Bottom which is generated s
by the process computer has inadequate sample intervals i
Parameters are sampled and printed out on a 60-second interval rather than the recommended 10-second interval.
Also, the strip chart recorders' chart speed of 2 cm/hr may not permit discrimination of parameter values with the precision needed for'an adequate post-trip review.
[
T PECo Response i
The combined capabilities of the post-trip log, sequence of events log, and strip chart recorders provide the
- information necessary to perform the post-trip review.
i The 60-second interval on the post-trip log provides a l
gross' overview of the event.
The strip chart recorders j
identify any significant variations in the parameters j
1 not reflected on the post-trip log.
Additionally, the j
sequence of events log is utilized to determine those l
parameters which experience significant deviations in i
values.
i l
l The 2 cm/hr strip chart speed does not affect its j
primary function, which is to analyze the magnitude of l
l the parameter's deviation.
The time at which a significant deviation occurs is obtained from the l
l sequence of events log data.
i 2)
NRC Noted Deviation
)
The parameters selected for the post-trip and sequence of events logs at Peach Bottom do not include all of 4
those identified by the NRC as required for the " good t
practices" approach.
i j
PECo Response I
i The parameters not included in Peach Bottom logs are explained below:
i i
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Mr. John F.
Stolz October 16, 1985 Page 3 Sequence of Events Log:
Parameter Explanation Safety Injection The initiating signals are logged'in lieu of the logic output signals for HPCI and RCIC.
One of the two initiating signals (High Drywell Pressure) for LPCI and core spray is logged and the other signal (reactor water level) is recorded on the post-trip log.
This combination provides the information necessary to perform the post-trip review.
Containment Isolation The initiating signals of primary containment isolation (i.e., drywell high pressure; main steam line high flow, high i
radiation, and leak detection; and reactor water level - lo e
and lo-lo) are logged in lieu of the logic output signals.
Control Rod Position Adequate post-trip review has been possible without this parameter.
f Turbine Bypass The function of this data in Valve Position post-trip review of boiling water reactors is not apparent.
i t
Recirculation Recirculation M-G set breaker Pump Status trip signals are provided as an indication of recirculation pump status.
AC and DC System Breaker position information Status (Bus Voltage) for the 4kv load center feeder breakers, the diesel generator 4kv breakers, i
and the 13kv unit auxiliary bus feeder breakers is provided instead of bus voltage.
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i
[
I
Mr.' John F. Stolz October 16, 1985 Page 4 Safety Injection The reactor water level Flow strip charts are utilized to ascertain pump flow.
Post Trip Log Parameter Explanation Containment Radiation The parameter's strip chart is utilized for analysis.
Drywell Pressure The parameter's strip chart is utilized for analysis.
Suppression Pool
.The suppression pool temperature Temperature monitoring systems's strip chart is utilized for analysis.
3)
NRC Noted Deviation For the storage and retrieval of information gathered by the sequence of events and time history recorders, the computer generated data will be presented in a readable and meaningful format, but the 2 cm/hr strip chart recorder speed represento a record format that may not be readable to the accuracy needed for a post-trip review.
PECo Response The response to the first deviation regarding strip chart recorder speed is applicable to this deviation.
The strip chart output is primarily used for analysis of the magnitude of the parameter's deviation.
The time at which the deviation occurs is obtained from the sequence of events log data.
O While we believe that our existing data and information capabilities are adequate to perform a post-trip review, we are proposing to include an upgrade of the sequence of events and
. post-trip logs in a planned. process computer upgrade.
The upgraded computer is scheduled to be operational following the third refueling outage for both Units 2 and 3 commencing after 1985.
Based on our current outage schedule projections, the upgrade should be complete on Unit 2 by late 1989, and on Unit 3 by mid-1990.
The upgrade will include the following changes to t
1 L
I
Mr. John F. Stolz October 16, 1985 Page 5 the sequence of events and post-trip logs:
1.
The sequence of events log will continue to have a better than or equal to 100 millisecond time discrimination.
2.
The post-trip log will have a sample interval of ten seconds in keeping with the " good practices" approach recommendation.
3.
The following parameters will be added to the sequence j
of events and post-trip logs:
Parameter SOE Post Trip i
Containment Radiation
'X Suppression Pool Temp X
Drywell Pressure X
Reactor Water Level - Lo-Lo-Lo (LPCI and core spray initiation signal)
X Safety Injection Flow (!IPCI, RCIC, RHR, and core spray)
X Control Rod Position (all rods full-in)
X With the completion of the process computer upgrade, Philadelphia Electric Company will be in conformance with all of the " good practices" approach recommendations except for the inclusion of Turbine Bypass Valve Position in the sequence of events' log.
Mr. John F. Stolz October 16, 1985 Page 6 If you have any questions or require additional information, please do not hesitate to contact us.
Very truly yours,
,X h I'
l_ {
cc:
Dr. T.
E. Murley, Administrator, Region I, USNRC T.
P. Johnson, Resident Site Inspector I
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