ML20148N535
| ML20148N535 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 03/22/1988 |
| From: | Sieber J DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| GL-83-28, NUDOCS 8804070110 | |
| Download: ML20148N535 (6) | |
Text
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$Nppqwt PA WM404 March 22,~1988 U. S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, DC 20555
Reference:
Beavor Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Goncric Letter 83-28 Gentlemen:
By letter dated July 22, 1986,,
the NRC provided a
Draft Technical Evaluation Report (TER) on Goncric Letter 83-28, Item 1.2 for Beaver Valley Unit No. 2 which was based on our March 30, 1984 submittal.
By request of your letter, a telephone conference was held with the
- NRC, and we provided the additional information requested in the Draft TER.
As a
followup to that conference call, attached is a summary of this additional information.
This information is similar to the information provided for Beaver Valley Unit No. 1 on this same subject.
If you have any questions regarding this information, please contact my office.
Very truly yours, 43/*.
. D.
Sieber Vice President Nuclear Group Attachment cc:
Mr. J. Beall, Sr. Resident Inspector Mr. W. T. Russell, NRC Region I Administrator Mr.
P. Tam, Project Manager Director, Safety Evaluation & Control (VEPCO) hN i i 8804070110 880322 PDR ADOCK 05000412 P
4
- 4 Response to Draft Technical Evaluation Report on Generic Letter 83-28, Item 1.2 NRC Request:
The information supplied in response to Generic Letter 83-28 does not indicate that the post-trip review data and information capabilitics are adequato in the following areas:
1.
Parameters Recorded:
Based upon the information contained in the submittal, all of the parameters specified in Part 2 of the draft TER that should be recorded for use in a
post-trip review are not recorded.
Attached is Table 1
that identifies the desired paramotors and discrepancies.
Response
Each of the identified paramotor discrepancies listed in Table 1 are recorded in the following manner:
Time History Recorders in Main Control Room a.
Containment Pressure 2LMS-PR950
-5 to +55 psig on Vertical Board A 2LMS-PR106 0 to 180 psia on Vertical Board A b.
Containment Sump Level 2DAS-LR220 0 to 12 inches on Vertical Board A 2RSS-LR151 0 to 225 inches on Vertical Board A c.
Primary System Flow Primary System Flow is not recorded, however, other recorded instruments are available to determine if sufficient flow cold exists to assure core cooling (i.e.,
hot leg leg aT).
d.
Containment Radiation 2RMR*RQR206 10' to 107E/hr High Range Area Monitor 2RMR*RQR207 10 to 10'R/hr High Range Area Monitor 2RMR*RQR303 10-' to 10-2 uCi/cc (gas) Cnmt.
Airborne Monitor 10-" to 10- 5 uCi/cc (particulate)
Cnmt. Airborne Monitor
R:sponto to Draft TcchnicG1 Evoluction R; port on GenOric Lottor 83-28, Ittm 1.2 Pag 3 2 Scquence of Events (SOE) Recorder Points a.
Containment Isolation Y6010D Containment Isolation Phase A Signal Y6070D Containment Isolation Phase B Signal b.
Control Rod Position Not recorded on SOE Recorder.
Emergency Operating Procedures require operator to verify all rods are fully inserted following any reactor trip.
c.
Containment Radiation Nonc required:
See note 2 on Tabic 1.2-1 of TER d.
Primary System Flow F0400D RCL A 1
Low Flow F0440D RCL C
1 Low Flow F0401D RCL A 2
Low Flow F0441D RCL C
2 Low Flow F0402D RCL A 3
Low Flow F0442D RCL C
3 Low Flow F0420D RCL B 1
Low Flow F0421D RCL B 2
Low Flow F0422D RCL B 3
Low Flow e.
Safety Injection; Flow, Pump / Valve Status Y3915D Safety Injection Signal Y922D Low Head SI PP A Start /Stop YO923D Low Head SI PP B Start /Stop Y3417D Chg. PP 21A Mot Bkr Closed /Open Y3418d Chg. PP 21B Mot Brk Closed /Open Y3419D Chg. PP 21C Mot Brk A Closed /Open Y3420D Chg. PP 21C Mot Brk B Closed /Open Y3401D Low HD SI PP 21A Mot Brk Closed /Open Y3402D Low HD SI PP 21B Mot Brk Closed /Open f.
MSIV Position MSIV position is not recorded on the SOE Recorder.
MSIV position indicators are located in the main control room benchboard - Section C.
g.
Steam Generator Pressure PO404D SGA Lo Stm P 2 Part Rx PO405D SGA Lo Stm P 3 Part Rx PO406D SGA Lo Stm P 4 Part Rx PO424D SGB Lo Stm P 2 Part Rx PO425D SGB Lo Stm P 3 Part Rx PO426D SGB Lo Stm P 4 Part Rx PO444D SGC Lo Stm P 2 Part Rx PO445D SGC Lo Stm P 3 Part Rx PO446D SGC Lo Stm P 4 Part Rx
R:cponsa to Draft TCchnical Evoluction R3 port on G3n3ric Lettor 83-28, Item 1.2 Page 3 i
2.
Time History Recorders:
Time History Recorders, as described in the submittal, do not l
meet the minimam performance characteristics (i.e., 10 second j
sample interval with information 5 minutes prior to trip to 10 minutes after trip).
1
Response
Beaver Valley Unit No. 2 utilizes strip chart recorders to obtain a time history of the following parameters:
Neutron Flux, power 0 to 120%
2NME-NR45 10-5 to 200%
2NME-NR55 Containment Pressure O to 180 psia 2LMS-PR106
-5 to +55 psig 2LMS-PR950 Containment Sump Level O to 12 inches 2DAS-LR220 0 to 225 inches 2RSS-LR151 RCS Pressure O to 3000 psig 2RCS-PR441 1700 to 2500 psig 2RCS-PR444 RCS Temperature O to 700F 2RCS-TR 410, 413 t
Main Steam Pressure O to 1200 poig 2 MSS-PF475 I
l Steam Generator Level O to 100%
2FWS-FR-478, 488, I
(narrow range) and 498 0 to 100%
2FWS-LR477 (wide range)
Main Steam Flow 0 to SMPPH 2FWS-FR-478, 488, l
and 498 Feedwater Flow 0 to 5 MPPH 2FWS-FR-478, 488, and 498 y
Primary System Flow is not recorded (see Response to Item 1).
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3.
Data output Format As described in the submittal, the recorded data may not be i
output in a readabic and meaningful format.
Response
At the time of Beaver Valley Unit No. 2 initial response in 1984, many of the formats had not been finali:cd.
These formats are now finalized and in use.
All necessary information (time, 1
i
- value, description, etc) is displayed for analog and digital information.
Response to Draft Technical-Evaluation Report on Generic Letter 83-28, Item 1.2 Page 4 4.
Data Retention Capability The data retention procedures, as described in the submitta1, may not ensure that the information recorded for the post-trip review is maintained in an accessible manner for the life of the plant.
Response
Beaver Valley Unit No. 2 Technical Specification 6.10.1 requires retention for at least five (5) years for:
Records and logs of facility operation covering the time interval at each power level.
All reportable events.
This is the current requirement for maintaining quality records and is considered adequate.
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TABLE 1
Desirable PWR Parameters for Post-Trip Review (circled parameters are not recorded)
Time History SOE Parameter / Signal Recorder Reactor Trip s
l x
Safety Injection (1) x Containment Isolation Turbine Trip (1) x Control Rod Position Neutron Flux, Power x
(1) x Containment Pressure x
Containment Radiation Containment Sump Level Primary System Fressure (1) x x
Primary System Temperature (1) x x
Pressurizer Level (1) x Reactor Coolant Pump Status (1) x (1) x Primary System Flow Safety Inj.; Flow, Pump / Valve Status 3
MSIY Position Steam Generator Pressure x
Steam Generator Level (1) x x
Feedwater Flow (1) x x
Steam Flow l
(1)x x
Auxiliary Feedwater System; Flow.
(3) l Pump /Value Status AC and DC System Status (Bus Voltage) x Diesel Generator Status (Start /Stop, x
On/Off)
{
PORV Position x
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(1): Trip parameters (2): Parameter may be monitored by either an SOE or time history recorder.
(a) system flow recorded on an SOE l
(3): Acceptable recorder options are.:
recorder, (b) syster, flow recorded on a time history recorder, or (c) equipment status recorded on an SOE recorder.
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