ML20137A628
| ML20137A628 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 11/14/1985 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| GL-83-28, NUDOCS 8511260055 | |
| Download: ML20137A628 (5) | |
Text
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'Af Telephone (412) 393-6000 Nucleer Group hnSppYgport. PA 15077-0004 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Attn:
Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing Washington, DC 20555
Reference:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Draft Technical Evaluation Report on Generic Letter 83-28, Item 1.2 Gentlemen:
By letter dated October 17, 1985, the NRC provided a Draft Technical Evaluation Report (TER) on Generic Letter 83-28, Item 1.2 which was based on our November 4, 1983 submittal.
As per the request of your letter, a telephone conference was held on November 7,
1985 with the NRC reviewer and we provided the additional information requested in the Draft TER.
As a followup to that conference
- call, we are providing this information to document the exchange of information which occurred at that time.
Attached is a
summary of the additional information requested along with our response.
If you have any questions regarding this information, please contact my office.
5 Very tr ly yours, 8511260055 851114 PDR ADOCK 05000334
[/
P PDR
.V.
Carey Vice President, Nuclear cc:
Mr. W.
M. Troskoski, Resident Inspector U.
S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 U. S. Nuclear Regulatory Commission c/o Document Management Branch Washington, DC 20555 Director, Safety Evaluation & Control Virginia Electric & Power Company
(
P.O. Box 26666 7
One James River Plaza I
Richmond, VA 23261 l
o Rsuponce 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 capabilities are adequate in the following areas:
-1.
Based upon the information contained in the cubmittal, 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 parameters and discrepancies.
Response
Each of the identified parameters are recorded in the following manner:
a.
Containment Sump Level { Time History Recorder}:
LR-RS151, 0-90 inches on vertical board A b.
Steam Generator Pressure {SOE Recorder}:
Steam line press upstream of the MSIVs is provided at the following SOE points:
601 Loop'1A Steam Line Low Press 602' Loop 1B 603 Loop 1C 611 Loop 1A Main Steamline Press High 612 Loop 1B 613 Loop 1C c.
Steam Flow (Trip Parameter) {SOE Recorder}:
Beaver Valley 1 does not have a steam flow trip but has a
steam flow-feed flow. mismatch coincidenced with low steam generator level trip.
SOE points are:
623 Loop 1A Feedwater Fl. Greater than Steamline Fl.
624 640 Loop 1B 641 657 Loop 1C 658 625 Loop 1A Steamline High Flow CH3 626 CH4 642 Loop 1B CH3 643 CH4 659 Loop 1C CH3 660 CH4
R$dponto to Draft TER on~
G2n$ric L$tter 83-28, Item 1.2 Page 2 6
632 Loop 1A Steam Feedwater Flow Mismatch CH3 633 CH4 649 Loop 1B CH3 650 CH4 666 Loop 1C CH3 667 CH4 762 LP 1A Stm Gen Wtr Lvl & Fdwtr F1 L Reac Trp 770 LP 1B 776 LP 1C d.
PORV Position {SOE R'ecorder}:
Draft Incident Report requires listing the relief valves that lift.
Also, high line temperature recorded at SOE point:
105 Pressurizer PWR Relief Line Discharge Temp. Hi 1
2.
Time history recorders, as described in the submittal, do not meet the minimum performance characteristics (i.e., 10-second sample interval with information 5 minutes prior to trip to 10 minutes after trip.)
Response
Beaver Valley 1
utilizes strip chart recorders to obtain a time history of the following parameters:
Neutron Flux, Power 0-5 milliamps NR-NI-41, 42, 43, 44 Containment Pressure 0-200 psi PR-LM101 70 psig PR-LM100A Containment Sump Lvl.
0-90 inches LR-RS151 RCS Pressure 0-3000 psig PR-RC403 RCS Temperature 0-700*F TR-RC410, 413 Main Steam Pressure 0-1400 psig PR-MS474 Steam Generator Lvl.
0-100%
FR-MS478, 488, 498 (narrow range) 0-100%
LR-FW477 (wide range)
-Main Feedwater_ Flow 0-100%
FR-MS-478, 488, 498 Steam Flow 0-100%
FR-MS-478, 488, 498 Not recorded is RCS
- Flow, however, other instrume:. s are available to determine if sufficient flow exists to assure core cooling (i.e., hot leg-cold leg AT).
i
R;spones to-Draft TER on Gen 3ric Lstter 83-28, Item 1.2-Page 3 3.-
The data retention procedures, as described in the submittal, 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 1
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 since we are developing a reactor trip-reduction program.
This program will aid,,in identifying trends in reactor trips so that corrective action can be taken to further reduce future reactor trips.
TABLE 1 Desirable PWR Parameters for Post-Trip Review (circled parameters are not recorded)
SOE Time History Recorder Recorder Parameter / Signal x
Reactor Trip (1)x Safety Injection x
Containment Isolation (1) x Turbine Trip x
Control Rod Position (1) x x
Neutron Flux. Power x
x Containment Pressure (2)
Containment Radiation Containment Sump Level (1)x x
Primary System Pressure (1) x Primary System Temperature x
(1)x Pressurizer Level (1) x Reactor Coolant Pump Status (1)x x
Primary System Flow (3)
' Safety Inj.; Flow. Pump / Valve Status x
MSly Position x
Steam Generator Pressure (1) x x
Steam Generator Level (1) x x
Feedwater Flow (1)@
x Steam Flow (3)
Auxiliar'y Feedwater System; Flow.
Pump /Value Status x
AC and DC System Status (Bus Voltage) x Diesel Generator Status (Start /Stop.
On/0ff)
PORY Position (1): Trip parameters (2): Parameter may be monitored by either an SOE or time history recorder.
- (3): Acceptable recorder options are: (e) system flow recorded on an SOE recorder. (b) system flow recorded on a time history recorder, or (c) equipment status recorded on an SOE recorder.
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