ML20076K795
| ML20076K795 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 07/12/1983 |
| From: | Bayne J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.1, TASK-TM JPN-83-66, NUDOCS 8307180108 | |
| Download: ML20076K795 (5) | |
Text
123 Main Street
' ' " White Plains, New bk 10C41 316 681.6240
- > NewWrkPbwer tra"!cn.mt 4ff Authority
-e+-e July 12, 1983 JPN-83-66 Director of Nuclear Reactor Regulation U.S.
Nuclear Regulatory Commission Washington, D.C.
20555 Attention:
Mr. Domenic B.
Vassallo, Chief Operating Reactor Branch No. 2 Division of Licensing
Subject:
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 NUREG-0737 Post-TMI Requirements Item II.F.1.4 Containment Pressure Monitor Item II.F.1.5 Containment Water Level Monitor
References:
1.
NRC letter, D.B. Vassallo to L.W. Sinclair, dated February 2, 1983.
2.
NYPA letter, J.P.
Bayne to D.B. Vassallo, dated June 23, 1983 (JPN-83-58).
Dear Sir:
In Reference 1 the NRC requested additional information concerning the subject modifications.
This information was provided in Reference 2. to this letter replaces the attachment to Reference 2 which has been revised to correct inaccuracies which arose in the transmittal of data to the Authority from our contractor.
If you have any questions, please do not hesitate to contact Mr.
J.A. Gray, Jr. of my staff.
Very truly yours, fY&
A
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J.P.
Bayne Executive Vice President Nuclear Generation cc:
Attached 8307180100 830712 8
PDR ADOCK 05000333 ll8 j
cc: Mr.
T. Linville i
Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 136 Lycoming, NY 13093
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ATTACHMENT 1 TO JPN 66 DATED July 12, 1983 o
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-. - o This attachment provides accuracies of the Pressure and Water Level Monitorin'g Systems (PMS and WLMS) including accuracies and response times of system components.
Response time is defined as the time required for output to reach 90% of final value following a step input :from 10%- to 90% of span. LOCA/HELB
'and post-DBE system accuracies are presented in Table 1.
Note that the PMS monitors reactor and drywell pressure,and the WLMS monitors water level in the suppression pool and the drywell.
Table 2 presents component ranges, accuracies, and time responses for the PMS.
Table 3 presents component ranges, accuracies, and time responses for the WLMS.
The magnitude and rate of change during a post-accident period of the four parameters being measured were analyzed to determine the accuracy and response times required for the reactor operator to adequately assess the conditions and take appropriate action.
The.valueslof these variables (reactor pressure, drvwell pressure, suppression pool level and drywell water level) have considerable design margin and the rate of change is predicted to be low during the extended post-accident period.
The total system time response was not calculated for the PMS and WLMS.
However, the largest component time response is140 seconds for an input step change of 80% of span.
(This refers to WLMS and-translates to an acceptable time response for a realistic step increment in torus water level).
Since the next largest component time response is an order of magnitude less, this component will largely determine the greatest system time response.
For the reactor PMS and for the drywell PMS and WLMS, the longest component time response is 3.5 seconds.
With the exception of the 40 second response time discussed above, accuracies and response times are consistent with ANSI /ANS 4.5-1980 requirements.
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TABLE 1 SYSTEM ACCURI.CIES Accuracy (% span)
LOCA/HELB POST /DBE MONITORED ITEM
-Reactor Pressure 1 3.6 1 1.3
-Drywell Pressure
+-3.6 1 1.3 (Low > Range)
Drywell Pressure 3.6 1 1.3
-(High Range)
Suppression ~ Pool Level 1 3.6
+ l.3 i
Drywell Level 1 9.5 1 3.5 1
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