ML20125B287
| ML20125B287 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 06/04/1985 |
| From: | Mcdonald R ALABAMA POWER CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| GL-83-28, NUDOCS 8506110368 | |
| Download: ML20125B287 (9) | |
Text
_
C lling Address Alab2ma Power Company -
- 7., ; *. -
600 North 18th Street Post Office Box 2641 Birmingham. Alabama 35291 Telephone 205 783-6090
. R. P. Mcdonald Senior Vice President Flintridge Build ng Alabama Power tre sm.!nem e etrc snie" June 4,1985
-Docket Nos. 50-348 364 Director, Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Attention: Mr. S. A. Varga Joseph M. Farley Nuclear Plant - Units 1 and 2 Response to NRC Draft Technical Evaluation Report for Item 1.2 of Generic Letter 83-28 Gentlemen:
-By letter dated May 10, 1985, the NRC issued a draft Technical Evaluation Report (TER) for Item 1.2 of Generic Letter 83-28. Attached is the Alabama Power Company response to the subject TER.
If there are any questions, please advise.
Yours very tr ly, R. P. Mcdonald RPM /RGW:ddb-D48 Attachment cc: Mr. L. B. Long Mr. E. A. Reeves Mr. W. H. Bradford Dr. J. N. Grace f
6 L
506110368 850604 I I ADOCK 05000348 p
i PDR
Attachment NRC Concern:
The sequence of events and time history recording equipment should monitor sufficient digital and analog parameters, respectively, to assure that the course of the reactor trip can be reconstructed. The parameters monitored should provide sufficient information to determine the root cause of the reactor trip, the progression of the reactor trip, and the response of the plant parameters and systems to the reactor trip.
Specifically, all input parameters associated with reactor trips, safety injections and other safety-related systems as well as output parameters sufficient to record the proper functioning of these systems should be recorded for use in the post-trip review. The parameters deemed necessary, as a minimum, to perform the post-trip review (ones-
- that would determine if the plant remained within its design envelope) are presented in Tables 1.2-1 and 1.2-2.
If the applicants' or licensees' SOE recorders and time history recorders do not monitor all of the parameters suggested in these tables, the applicant or licensee should show that the existing set of monitored parameters are sufficient to establish that the plant remained within the design envelope for the appropriate accident conditions; such as those analyzed in Chapter 15 of the plant Final Safety Analysis Report.
APCo Response:
The November 4,1983 APCo response to Section 1.2 of Generic Letter 83-28 contained a narrative description of the Post-Mortem Review Program, however, a listing of the analog parameters monitored was not submitted. Table A contains a listing of the analog parameters monitored for the Post-Mortem Review Program.
Also included in the November 4,1983 APCo submittal was a listing of the SOE parameters monitored at Farley Nuclear Plant. The SOE Program print capability has subsequently been expanded to include all solid state protection system part reactor trip inputs.
These additional parameters are listed in Table B.
These additional parameters, in conjunction with the SOE parameters submitted in. the November 4,1983 response, should address all the parameters 11dentified in Table 1.2-1 of the Technical Evaluation Report with the exception of control rod position; containment radiation; containment sump level; safety injection flow and pump / valve status; MSIV position; auxiliary feedwater system flow and pump / valve status; and PORY position. The following information, L
although not associated with the Sequence of Events and Post-Mortem Review Programs, is submitted to support alternate trip review capabilities for those parameters.
- 1) Control Rod Position Equivalent time history recording capability is provided by combination of the rod position and redundant measurements programs. The combination of r
these programs provides a rod vs. rod and rod vs. bank deviation comparison based upon a twelve (12) step cluster limit. This position monitoring and deviation comparison is performed at periodic intervals or upon detection of I-i e
y e...,
,,e,w,g,---
a
.we-m.,m-~.-..,,,......,w..,. -,,
.gm,,_,,w.ee,
,,,r.n.,
.,,..,.,,-.~e,-w.,a,,.-,-,,-,-mem-.,--n.m n,,n,m,,.,-..,-n.r
,,, - -.m_--..,w,.,,a
Page 2
- 1) Control Rod Position (continued) a rod position change input from the Digital Rod Position Indication system. When a deviation condition exists, rod deviation annunciation and hard copy printout is supplied to the control room.
Upon detection of a reactor trip event, deviation comparison is suppressed for ten (10) seconds to prohibit nuisance alarms due to rod travel through the core. Deviation comparison is then resumed at the end of this ten (10) second interval. The deviation comparison can be used by plant personnel to evaluate a stuck, dropped or misaligned rod condition.
" Rod on Bottom" indication is provided to the operator (s) by a periodically scanned digital input to the plant computer. This input is processed for changes in state approximately every two (2) seconds with changes logged to the alarm typewriter.
- 2) Contairment Radiation Containment radiation is monitored by radiation monitors R2, R7, R11, R12, R24 A and B, and R27 A and B.
Monitors R2 and R7 are area radiation monitors which measure gross gama activity in the surrounding area. Each monitor has a remote readout unit consisting of a readout meter and an audio and visual alarm, a control console in the main control room which provides meter readout, alarm lights, indicating lights and control switches, and a strip chart which maintains a record of the output of each monitor. Monitor R11 is a containment air particulate monitor which takes an air sample for the containment atmosphere and measures the air particulate gamma radioactivity. Monitor R12 measures the gaseous gamma radioactivity in containment by taking an air sample from the containment atmosphere after it passes through the air particulate monitor. Monitors R11 and R12 have multipoint recorders located in the control room. Monitors R24 A and B, containment purge exhaust flow gas monitors, are dual channel off-line radiogas monitors which utilize a beta sensitive scintillation detector.
Main control board annuciators are provided and a recorder is provided for the train A and train B channels.
R27 A and B are high range containment area radiation monitors utilized for accident and post-accident monitoring. Each monitor consists of an ion chamber located in containment and a readout module in the control room.
Each readout is a multi-range meter with alert and high alarm lights. The modules are located on the gaseous radiation monitoring system panel with a recorder provided for monitor indication.
Monitors R2, R7 and R27 A and B are inputs to the SPDS and will supply pre and post-trip review capabilities when the SPDS is operational. SPDS is currently scheduled to be operational during the eighth refueling outage for Unit 1 and the fifth refueling outage for Unit 2.
c Page 3
- 3) Containment Sump Level The containment recirculation sump serves each of the redundant trains of the ECCS and containment-spray systems.
Indication of containment level near the recirculation sumps is provided on the main control board and recorded. The recorder is powered by an inverter which takes AC power from an emergency motor control center backed by a diesel generator.
If AC power is lost to the inverter, a DC source instantly feeds power to the inverter until _ the AC source is restored. Containment sump level is scheduled for input to the SPDS with pre and post-trip review capabilities.
4)
Safety Injection Flow and Pump / Valve Status Charging pump discharge header flow and RHR loop flow on Trains A and B are input to~ the plant computer. RHR and charging pump breaker status is monitored by the plant computer through digital inputs which are processed for changes'in state approximately every two (2) seconds with any changes in state logged to the alarm typewriter. Valve status is provided by main control board indication.
Safety injection flow and pump / valve status is verified by emergency response procedures when necessary.
- 5) MSIV Position Each main steam line at Farley Nuclear Plant has two main steam isolation valves installed in series-(i.e., 3369 A, B and C are installed in series with downstream valves 3370 A, B, and C for each unit.) The upstream valve, 3369 A, B and C, positions are digital inputs to the plant computer. These
. inputs are processed for changes in state at approximately two (2) second intervals with changes.in state logged to the alann typewriter.
Sequence of-Events inputs from the MSIV's consist of turbine trip on valves 3369A, B or C, turbine trip on valves 3370A, B or C, and overspeed protection on valves 3370 A, B or C.
Position indication for all the MSIV's is provided on the main control board.
6)
Auxiliary Feedwater System Flow and Pump / Valve Status 9
- All automatic valves in the Auxiliary Feedwater System are verified fully open whenever the system is placed in automatic control or when above 10%
rated thermal power by procedures. Flow control valves 3227 A, B and C and 3328 A, B and C control solenoids are monitored by the plant computer and
. provide indication of an auto start full open condition. These digital inputs are periodically scanned and processed for changes in state approximately every two (2) seconds with any changes in state logged to the plant computer alarm typewriter. Steam admission and stop valve control solenoids are also monitored by the plant computer with changes in state logged to the alarm typewriter. Steam Generator Auxiliary Feedwater flows will be inputs to the SPOS with pre and post-trip capabilities.
i Page 4
- 7) PORV Indication PORY position is provided by main control board indication. PORV leak-by is monitored by main control board temperature alarm indication.
In addition, PRT level, temperature and pressure have main control board indication which can be monitored to determine the status of the PORV. Procedures are also in place which require that the PORY be verified fully closed with no evidence of leakage when pressurizer pressure falls below 2315 psig.
NRC Concern:
To support the post-trip analysis of the cause of the trip and the proper function of involved safety-related equipment, each analog time history data recorder should be capable of updating and retaining information from approximately five minutes prior to the trip until at least ten minutes after the trip.
APCo Response:
As stated in the November 4,1983 APCo response, all parameters included in the Post-Trip Review are collected for two (2) minutes before and three (3) minutes after the trip event at ten (10) second intervals. The required PWR parameters for Post-Trip Review identified in the draft TER include (1) Neutron Flux, Power, 2) Containment Pressure, 3) Containment Sump Level, 4) Primary System Temperature, 5) Primary System Flow, 6) Steam Generator Pressure, 7) Steam Generator Level, 8) Feedwater Flow, and 9) Steam Flow. All of the identified parameters, with the exception of Containment Pressure and Containment Sump Level, are inputs to the Post-Mortem Review Program at FNP.
In addition, all the identified parameters, with the exception of Primary System Flow and Steam Generator Pressure, are monitored by strip chart recorders. The recorders are powered by an inverter which is supplied AC power from an emergency motor control center. The motor control centers have an alternate DC power supply from the diesel generators.
In the event of loss of AC power to the inverter,
~ batteries instantaneously supply DC power to the inverter until the diesels come on-line. The diesels then supply DC power to the inverters until the AC source returns.
RGW/ddb:048
y, POIE-MDRfD1 REVIEW PROGRAM PAP #EIERS F0127A RCP 3 SEAL INJECTION FLOW (FI-127A)
F0129A RCP 2 SEAL INJECTION FLOW (FI-129A)
F0131A RCP 1 SEAL INJECTION FLOW (FI-131A)
F0400A RCL1 1 FLOW (FI-414)
F0401A RCL1 2 FLOW (FI-415)
F0402A RCL1 3 FLOW (FI-416)
F0403A S/G 1 FEEDWATER IN 1 FLOW (FI-477B)
N F0404A S/G 1 FEEDWATER IN 2 FLOW (FI-4763) l F0405A S/G 1 STEAM OUT 1 FLOW (FI-474B)
F0406A S/G 1 STEAM OUT 2 FLOW (FI-4758)
F0420A RCL2 1 FLOW (FI-424)
F0421A RCL2 2 FLOW (FI-425)
F0422A RCL2 3 FLOW (FI-426)
F0423A S/G 2 FEEDWATER IN 1 FLOW (FI-487B)
F0424A S/G 2 FEEDWATER IN 2 FLOW (FI-486B)
F0425A S/G 2 STEAM OUT 1 FLOW (FI-484B)
F0426A S/G 2 STEAM OUT 2 FLOW (FI-485B)
F0440A RCL3 1 FLOW (FI-434)
F0441A RCL3 2 FLOW (FI-435)
F0442A RCL3 3 FLOW (FI-436)
F0443A S/G 3 FEEDWATER IN 1 FLOW (FI-497B)
F0444A S/G 3 FEEDWATER IN 2 FLOW (FI-496B)
F0445A S/G 3 STEAM OUT 1 FLOW (FI-4948)
F0446A S/G 3 STEAM OUT 2 FLOW (FI-495B)
LO400A S/G 1 NARROW RANGE 1 LEVEL (LI-474)
LO401A S/G 1 NARROW RANGE 2 LEVEL (LI-475)
LO402A S/G 1 NARROW RANGE 3 LEVEL (LI-476)
LO403A S/G 1 WIDE RANCE LEVEL (LI-477)
LO420A S/G 2 NARROW RANGE 1 LEVEL (LI-484)
LO421A S/G 2 NARROW RANGE 2 LEVEL (LI-485)
LO422A S/G 2 NARROW RANGE 3 LEVEL (LI-486)
LO423A S/G 2 WIDE RANGE LEVEL (LI-487)
L0440A S/G 3 NARROW RANGE 1 LEVEL (LI-494)
LO441A S/G 3 NARROW RANGE 2 LEVEL (LI-495)
LO442A S/G 3 NARROW RANGE 3 LEVEL (LI-496)
L0443A S/G 3 WIDE RANGE LEVEL (LI-497)
LO480A PRESSURIZER 1 LEVEL (LI-459)
LO481A PSESSURIZER 2 LEVEL (LI-460)
LO482A PRESSURIZER 3 LEVEL (LI-461)
LO483A PRESSURIZER LEVEL CONTROL S.P.
N0031A SOURCE RANGE DET. 1 LOG Q N0032A SOURCE RANGE DET. 2 LOG Q N0035A INTER. RANGE LOW DET. 1 LOG Q N0036A-INTER. RANGE LOW DET. 2 LOG Q N0041A POWER RANGE 1 TOP DET. Q QUAD. 4 N0042A POWER RANGE 1 BOTTOM DET. Q QUAD. 4 N0043A POWER RANGE 2 TOP DET. Q QUAD. 2 N0044A POWER RANGE 2 BOTTOM DET. Q QUAD. 2 N0045A POWER RANGE 3 TOP DET. Q QUAD. 1 N0046A POWER' RANGE 3 BOTTCM DET. Q QUAD. 1 N0047A POWER RANGE 4 TOP DET. Q QUAD. ' 3 N0048A POWER RANGE 4 TOP DET. Q QUAD. 3 N0049A POWER RANGE CEUDIEL 1 Q QUAD. 4 NO350A PCWER RANGE CR WrEL 2 Q QUAD. 2
TABLE A SHEUr 2 OU 2
!~.".
N0051A POWER RANGE CHANNEL 3 Q QUAD. 1 j
N0052A POWER RANGE CHANNEL 4 Q QUAD. 3 j
P0398A TURB FIRST STAGE 1 PRESS. (PI-446) 1 P0399A TURS FIRST STAGE 2 PRESS. (PI-447)
P0400A S/G 1 STEAM OUT 1 PRESS. (PI-474) 4 PO401A S/G 1-STEAM OUT 2 PRESS. (PI-475)
PO402A S/G 1 STEAM OUT 3 PRESS. (PI-476)
'P0420A S/G 2 STEAM OUT 1 PRESS. (PI-484) i
" P0421A S/G 2 STEAM OUT 2 PRESS. (PI-485)
P0422A S/G 2 STEAM OUT 3 PRESS. (PI-486) i P0440A S/G 3 STEAM OUT 1 PRESS. (PI-494) l PO441A S/G 3 STEAM OUT 2 PRESS. (PI-495)
{
P0442A S/G 3 STEAM OUT 3 PRESS. (PI-496)
P0480A PRESSURIZER 1 PRESS. (PI-455)
PO481A PRESSURIZER 2 PRESS. (PI-456) i P0482A PRESSURIEER 3 PRESS. (PI-457)
PO483A PRESSURIZER 4 PRESS. (PI-444)
PO496A STEAM LINE HEADER-1 PRESS. (FI-464)
P1000A CONTAINMENT 1 PRESS. (PI-951)
P1001A CONTAINMENT 2 PRESS. (PI-952)
QO340A GENERATOR GROSS M.W.
T0400A RCL1 1 T-AVG (TI-412D) t T0401A RCL1 2 T-AVG (TI-411A)
T0403A RCL1 1 DELTA T (TI-412A)
T0404A RCL1 2 DELTA T (TI-411B)
T0406A RCL1 WIDE RANGE COLD LEG T (TR-410 PEN 1)
T0407A RCL1 OVERPOWER DELTA T 1 S.P.
(TI-412B)
T0410A RCL1 OVERTEMP DELTA T 1 S.P.
(TI-412C)
T0412A RCP 1 MOTOR STATOR WINDING TEMP T0418A S/G 1 FEEDWATER IN 1 TEMP i
T0419A RCL1 WIDE RANGE HOT LEG TEMP (TR-413 PEN 1)
T0420A RCL2 1 T-AVG (TI-422D) i T0421A RCL2 2 T-AVG (TI-421A)
T-423A RCL2 1 DELTA T (TI-422A) 4 T0424A RCL2 2 DELTA T (TI-4218)
T0426A RCL2 WIDE RANGE COLD LEG TEMP (TR-410 PEN 2)
T0427A RCL2 OVERPOWER DELTA T 1 S.P.
(TI-422B)
T0430A RCL2 OVERTEMP DELTA T 1 S.P. (TI-422C)
~
T0432A RCP 2 MOTOR STATOR WINDING TEMP T0438A S/G 2 FEEDWATER IN 1 TEMP i
T0439A RCL2 WIDE RANGE HOT LEG TEMP (TR-413 PEN 3)
T0440A RCL3 1 T-AVG (TI-432D) i T0441A RCL3 2 T-AVG (TI-431A)
T0443A RCL3 1 DELTA T (TI-432A)
T0444A RCL3 2 DELTA T (TI-431B)
T0446A RCL3 WIDE RANGE COLD LEG TEMP (TR-410. PEN 3)
T0447A RCL3 OVERPOWER DELTA T 1 S.P.
T0450A RCL3 OVERTEMP DELTA T 1 S.P.
T0452A RCP 3 MOTOR STATOR WINDING TEMP T0458A S/G 3 FEEDWATER IN 1 TEMP T0481A PRESSURIZER STEAM TEMP (TI-454) i 70496A RC T-REF (TR-408 PEN 2)
)
TC497A RCL AUCTIONEERED HIGH DELTA-T
{
T0499A RCL AUCTIONEERED HIGE T-AVG I
l
n TABLE B SHEETf 1 OF 2 SOE POIM'S l
F0400D RCL1 1 LO F PART RE F0401D RCL1 2 LO F PART RE F0402D RCL1 3 LO F PART RE F0404D STM GEN 1 LO FW F 1 PART RE 4
F0405D STM GEN 1 LO FW F 2 PART RE
~
F0406D STM LINE 1 HI F 1 SL ISOL PART F0407D STM LINE 1 HI F 2 SL ISOL PART i
F0409D LP 1 LO STM LINE P SI PART RE F0420D RCL2 1 LO F PART RE
" F0421D RCL2 2 LO F PART RE F0422D RCL2 3 LO F PART RE F0424D STM GEN 2 LO FW F 1 PART RE F0425D STM GEN 2 LO FW F 2 PART RE F0426D STM LINE 2 HI F 1 SL ISOL PART F0427D STM LINE 2 HI F 2 SL ISOL PART F0429D,
LP 2 LO STM LINE P SI PART RE F0440D RCL3 1 LO F PART RE F0441D RCL3 2 LO F PART RE F0442D RCL3 3 LO F PART RE F0444D STM GEN 3 LO IN F 1 PART RE F0445D STM GEN 3 LO FW F 2 PART RE F0446D STM LINE 3 HI F 1 Sp ISOL PART F0447D STM LINE 3 HI F 2 SL ISOL PART F0449D LP 3 LO STM LINE P SI PART RE LO400D STM GEN 1 LO L 1 PART RE j
LO401D STM GEN 1 LO L 2 PART RE LO403D STM GEN 1 LO LO L 1 PART RE LO404D STM GEN 1 LO LO L 2 PART RE LO405D STM GEN 1 LO LO L 3 PART RE LO420D STM GEN 2 LO L 1 PART RE LO421D STM GEN 2 LO L 2 PART RE LO423D STM GEN 2 LO LO L 1 PART RE LO424D STM GEN 2 LO LO L 2 PART RE L0425D STM CEN 2 LO LO L 3 PART RE LO440D STM GEN 3 LO L 1 PART RE LO441D STM GEN 3 LO L 2 PART RE LO443D STM GEN 3 LO LO L 1 PART RE i
b LO4440 STM GEN 3 LO LO L 2 PART RE LO445D STM GEN 3 LO LO L 3 FART RE l
LO480D PRESSURI2ER HI L 1 PART.RE j
LO481D PRESSURIEER HI L 2 PART RE LO482D PRESSURIZER HI L 3 PART RE 4
N0001D PWR RNG CH 1 HI Q HI SP PART RE N0002D PWR RNG CH 2 HI Q HI SP FART RE 4
N0003D PWR RNG CH 3 HI Q HI SP PART RE N0004D PWR RNG CH 4 HI Q HI SP PART RE N0006D PWR RNG CH 1 HI Q LO SP PART RE N0007D PWR RNG CH 2 HI Q LO SP PART RE N000eD PWR RNG CH 3 HI Q LO SP PART RE I
N0009D-PWR RNG CH 4 HI Q LO SP PART RE N0020D INTERM RNG 1 HI Q INITIATE RE t
N0021D INTERM RNG 2 MI Q INITIATE RE N0025D PWR RNG CHAN 1 HI Q RATE PART RE i
N0026D FWR PJ!G CHAN 2 HI Q RATE PART RE N0027D
?WR RNG CHAN 3 HI Q RATE PART RE
~. -. -
TABLE B SPE!r 2 T 2 N0028D PWR RNG CHAN 4 HI Q RATE PART RE N0030D 80URCE RNG 1 HI Q INITIATE RE N0031D SOURCE RNG 2 HI Q INITIATE RE P0396D TB BYD OIL LO P 1 PART RE P0397D TB BYD OIL Lo P 2 PART RE P0398D TB BYD OIL LO P 3 PART RE P0404D STEAM LINE DP1 LOW P1 SI PART RE s
P040SD STEAM LINE DP2 LOW P1 SI PART RE PO406D STEAM LINE'DP3 LOW P1 SI PART RE PO408D STEAMLINE DP 4 LOW P1 SI PART RE PO409D STEAMLINE DP 5 LOW P1 SI PART RE PO410D STEAMLINE DP 6 LOW P1 SI PART RE PO424D STEAMLINE DP 1 LOW P2 SI PART RE P0425D STEAMLINE DP 2 LOW P2 SI PART RE i
P0426D STEAMLINE DP 3 LOW P2 SI PART RE PO428D STEAMLINE DP 4 LOW P2 SI PART RE P0429D STEAMLINE DP 5 LOW P2 SI PART RE PO430D STEAMLINE DP 6 LOW P2 SI PART RE P0444D STEAMLINE DP 1 LOW P3 SI PART RE PO445D STEAMLINE DP 2 LOW P3 SI PART RE PO446D STEAMLINE DP 3 LOW P3 SI PART RE P0448D STEAMLINE DP 4 LOW P3 SI PART RE P0449D STEAMLINE DP 5 LOW P3 SI PART RE P0450D STEAMLINE DP 6 LOW P3 SI PART RE P0480D PRESSURIZER HI P 1 PART RE-PO481D PRESSURIZER HI P 2 PART RE PO482D PRESSURIZER HI P 3 PART RE P0484D PRESSURIZER LO P 1 PART RE P0485D PRESSURIZER Lo P 2 PART RE PO486D PRESSURIZER LO P 3 PART RE P0489D PREsUZER LO P 1 SI PART RE PO490D PRESUZER LO P 2 SI PART RE P0491D PRESUZER LO P 3 SI PART RE P1000D CONTAINM HI P 1 SI PART RE P1001D CONTAINM HI P 2 SI PART RE P1002D CONTAINM HI P 3 SI PART RE T0400D RCL1 OVERPWR DT 1 PART RE T0403D RCL1 OVERTEMP DT 1 PART RE T0420D RCL2 OVERPWR DT 1 PART RE T0423D RCL2 OVERTEMP DT 1 PART RE T0440D RCL3 OVERPWR DT 1 PART RE T0443D RCL3 OVERTEMP DT 1 PART RE V0320D RCP BUS UNDER VOLT PART RE V0321D RCP BUS UNDER VOLT PART RE RCP BUS UNDER VOLT PART R V0322D RCP BUS UNDER FREQ PART R4 YO320D E
Y0321D RCP BUS UNDER FREQ PART RE YO322D RCP BUS UNDER FREQ PART RE YO391D TB STOP VLV A CL PART RE Y0329D TB STOP VLV B CL PART RE Y0393D TB STOP VLV C CL PART RE YO394D TB STOP VLV D CL PART RE
-