ML19336A651
| ML19336A651 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 10/16/1980 |
| From: | NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML19336A648 | List: |
| References | |
| NUDOCS 8010300422 | |
| Download: ML19336A651 (9) | |
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DOCKET NO. 50-245 ATTACHMENT MILLSTONE NUCLEAR POWER STATION, UNIT NO. 1 PROPOSED TECHNICAL SPECIFICATION CIIANGES FOR SCRAM DISCllARGE VOLUME SYSTEM OCTOBER, 1980 l-Q2 8010300 l
DESCRIPTION OF CHANGES AND SAFETY EVALUATION
SUMMARY
The proposed changes include adding scram discharge volume (SDV) rod block 4
functions and surveillance requirements for SDV vent and drain valves to the Technical Specifications. The two (2) conditions for initiation of
.controi rod block that have been added to the Technical Specifications are for high water level in the SDV system and when the SDV scram trip is I
bypassed. The inclusion of the above SDV rod block functions in the Technical i'
Specifications provides additional limiting conditions of operation. The
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- proposed surveillance requirements will increase the reliability of the SDV system.
1 Pursuant to'10CFR50.59, these changes have been reviewed and it has been determined that' they do not involve any unreviewed safety questions in that they do not increase the probability of occurrence or the consequences of j
- an accident or malf unction of equipment, create a possibility for a different
' type of accident or malfunction, or reduce the margin of safety as defined in the Technical Specifications.
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TABLE 3.2.3 INSTRUMENTATION THAT INITIATES R0D BLOCK Minimum Number of Ooerable Instrument Channels per -
Trip System (l)
Instrument Trip Level Setting 2
APCM Upscale (Flow Biased)
See' Spciification 2.1.28 2
APRM Downscale 3, 3/125 Full Scale 1 (6)
Rod Block Monitor Upscale (Flow Biased) 1 65 w + 42 (2)-
1 (6)
Rod Block Monitor Downscale
?; 3/125 Full Scale 3
IRM Downscale (3)
?; 3/125 Full Scale 3
IRM Upscale 5,108/125 Full Scale 2
SRM Detector not in Startup Position (4) 2 (5)
SRM Upscale '
5,105 counts /sec.
1 Scram Discharge Volume - Water Level High
< 18 gallons 1
Scram Discharge Volume - Scra~n Trip Bypassed N/A (1 )
For the Startup/ Hot Standby and Run positions of the Reactor Mode Selector Switch, there stall be two operable or tripped trip systems for each function except the SRM rod blocks; IRM downscale are not operable in the RUN position and APRM downscale need -not be operable in the Startup/ Hot Standby mode.
If the first colur.n cannot be met for one of the two trip systems, this condition may evist for up to seven days provided that during that time the operable system is functionally tested immediately and daily thereafter; if this conoi. tion lasts longer than seven days, the system shall be tripped.
If the first column cannot be met for both trip systems, the systems shall be tripped.
(2) W is the total' core flow in percent of design (69 x 106 #/ hr. ).
Trip level setting is in percent of full power.
(3)
IRM downscale may be bypassed when it is on its lowest range.
(4) This function may be bypassed when the count rate is 2,100 cps or when all IRM range switches are above Positior. 2.
(5) One of these trips may be bypassed. The SRM function may be bypassed in the higher IRM ranges when the IRM upscale rod block is operable.
Amendment No. f 3/4 2-5
Table 3.2.3 Continued Instrumentation Thr.t Initiates Rod Block (6)
The trip may be bypassed when the reactor power is < 30% of rated. An RBM channel will be considered inoperable if there are less than half the total number of normal inputs from any LPRM level.
Amendment No f 3/4 2-Sa
TABLE 4.2.1 MINIMUM TEST AND CALIBliATION FREQUENCY FOR CORE COOLING INSTRUMENTATION R0D BLOCKS AND ISOLATIONS Instrument Channel Instrument Functional-Test (2)
Calibration (2)
, Instrument Check (2)
ECCS Instrumentation 1.
Reactor Low-Low Water. Level (1 )
Once/3 Months 2.
Drywell High Pressure (1 )
Once/3 Months 3.
Reactor Low Pressure (Pump Start)
(1 )
Once/3 Months 4.
Reactor Low Pressure (1 )
' Once/3 Months (Valve-Permissive) 5.
APR LP Core Cooling. Pump Interlock (1 )
Once/3 Months 6.
Containment Spray Interlock (1 )
Once/3 Months 7.
Loss of Normal Power Relays '
Refueling Outage None i
8.
Power Available Relays (1) (5)
None 9.
Reactor High Pressure Once/3 Months
- Rod Blocks 1.
APRM Downscale (1) (3)
Once/3 Months (1) 2.
APRM Flow Variable (1) (3)
Once/3 Months (1 )
3.
IRM Upscale (6)
(6)
(6) 4.
IRM Downscale (6)
(6)
(6) 5.
RBM Upscale (1) (3)
Once/3 Months (1 )
6.
RBM Downscale (1) (3)
Once/3 Months (1 )
7.
SRM Upscale (6)
(6)
(6) 8.
SRM Detector not in Startup Position (6)
(6)
(6) 9.
Scram Discharge Volume - Water Level High Refueling Outage Refueling Outage 10.
Scram Discharge Volume - Scram Trip Bypassed Refueling Outage None
. Main Steam Line Isolation l.
Steam Tunnel High Temperature Refueling Outage Refueling Outage 2.
Steam Line High Flow (1)
Once/3 Months Once/ Day
,3.
Steam Line Low Pressure (1) (3)
Refueling Outage None
- 4.. Steam Line High Radiation (1) (3)
Once/3 Months (4)
Once/ Day Amendment No. M, $7 3/4 2-6
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LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 5.
During operation with limiting control 4.
Prior to control rod withdrawal for rod patterns, as determined by the startup or during refueling, verify reactor engineer, either:
that ut least two source range channel; have an observed count a.
Both RBM channels shall be operable; rate of at least three counts per or second.
b.*
Control rod withdrawal shall be 5.
When a limiting control rod pattern blocked; or exists, an instrument functional test of the RBM shall be performed prior c.
The operating power level shall be to withdrawal of the designated lir.dtad so that the MCPR will rod (s) and daily thereafter.
rema 2a above 1.06 assuming a single erro.- that results in complete C.
Scram Insertion Times withdrawal of any single operable control rod.
1.
During each operating cycle, each operable control ' rod shall be C.
Scram Insertion Times subjected to scram time tests from the fully withdrawn position.
If
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The average scram insertion time, based testing is not accomplished during on the deenergization of the scram pilot reactor power operation, the measured valve solenoids as time zero, of all scram insertion times shall be operable control rods in the reactor extrapolated to the reactor power power operation condition shall be no operation condition utilizing greater than:
previously determined correlations.
% Inserted From Average Scram 2.
The scram discharge volume drain and Fully Withdrawn Insertion Times (Sec.)
vent valves shall be verified open at least onct per month.
5 0.375 20 0.900 3.
The following conditions of opera-50 2.000 bility of the scram discharge volume 90 3.500 drain and vent valves shall be verified at least once per operating cycle in accordance w th Section 3.13, Inservice Inspection:
Amendment No. 16, 47 3/4 3-4
i LIMITING CONDITI0fi FOR OPERATION SURVEILLANCE REQUIRE;1ENT a.
Closing time after signal' for control rods to scram 7-and b.
Verification of opening when. scram signal is reset and when the scram discharge volume trip is bypassed.
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l Amendment No. 75, A7 3/4 3-4a I
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 2.
Tne average of the scram insertion times i
D.
Control Rod Accumulators for the three fastest control rods of all groups of four control rods in a two by Once a shift, check the status in the two array shall be no greater than:
control room of the pressure and level alarms for each accumulator.
% Inserted From Average Scram Fully Withdrawn Insertion Times (sec.)
5 0.398 20 0.954 50 2.120 90 3.800 l
3.
a.
The maximum scram insertion time for 90%
insertion of any operable control rod shall not exceed 7.00 seconds.
b.
The scram discharge volume drain and vent valves will close in less than 30 seconds after receipt of a signal for control rods to scram.
D.
Control Rod Accumulators At all reactor operating pressures, a rod accumulator may be inoperable provided that no other control rod in the nine-red syvare array around this rod has a:
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Directional control valve electrically disarmed while in a non-fully inserted position.
3.
Scram insertion greater than maximum permission insertion time.
i Amendment No. A 3/4 3-5 i
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r LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT If a control rod with an inoperable accumulator is inserted " full-in" and its directional control valves are electrically disarmed, it snall not be considered to have an inoperable accumulator.
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1 Ii Amendment No. #
3/4 3-Sa