ML20092P742

Proposed Tech Spec Changes,Adding Tables Re Checks,Calibrs, Tests & Instrument Operating Requirements for 480-volt Ac Essential Bus Undervoltage Protection

ML20092P742
Person / Time
Site:	Fort Saint Vrain
Issue date:	06/26/1984
From:	PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20092P735	List: ML20092P734 ML20092P738 ML20092P742
References
NUDOCS 8407090327
Download: ML20092P742 (19)

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• Fort St. Vrain #1 -

Technical Specifications '

l Amendment No.  ;

j Page 4.4-1 1

I l 4.4 INSTRUMENTATION AND CONTROL SYSTEMS - LIMITING CONDITIONS FOR OPERATION l

Applicability Applies to the plant protective system and other critical instrumentation and controls.

Objective To assure the operability of the plant protective system.

and other critical instrumentation by defining the minimum operable instrument channels and trip settings.

l Specification LCO 4.4.1 - Plant Protective System and Other l Critical Instrumentation and Controls, Limiting Conditions for Operation The limiting conditions for the plant protective system l and other critical instrumentation and controls are shown on l Tables 4.4-1 through 4.4-5. These tables utilize the following definitions:

Degree of Redundancy - Difference between the number of operable channels and the minimum number of operable channels which when tripped will cause an automatic system trip.

Ooerable Channel - A channel is operable if it is capable of fulfilling its design functions.

Inoperable Channel - Opposite of operable channel.

l Tables 4.4-1 through 4.4-5 are to be read in the following manner: If the minimum operable channels or the minimum degree of redundancy for each functional unit of a table cannot be met or cannot be bypassed under the stated permissible bypass conditions, the following action shall be taken:

For Table 4.4-1, the reactor shall be shut down within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, except that to facilitate maintenance on the Plant Protective System (PPS) moisture monitors, the moisture monitor input trip functions to the Plant Protective System which cause scram, loop shutdown, circulator trip, and steam water dump may be disabled for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. During the time that the Plant Protective-System moisture monitor trips are disabled, an observer in direct communication with the reactor operator shall be positioned in the control room in the location of pertinent instrumentation. The observer shall continuously monitor the primary coolant moisture levels indicated by at least two moisture monitors and the primary coolant pressure indications, and shall alert the reactor operator to any indicated moisture or pressure change.

8407090327 840626 PDR ADOCK 05000267 P py

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Fort St. Vrain #1 Technical Specifications '

Amendment No.  ;

Page 4.4-2 For Table 4.4-2, the, affected loop shall be shut down within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

For Table 4.4-3, the affected helium circulator shall be shut down within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

For Table 4.4-4, the reactor shall be shut down within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

l For Table 4.4-5, the affected 480V AC essential bus shall l be declared inoperable, and the appropriate action for.

l that system shall be followed.

If, within the indicated time limit, the minimum number of operable channels and the minimum degree of redundancy can be reestablished, the system is considered normal and no further action needs to be taken. ,

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Fort St. Vrain #1 2 Technical Specifications  ;

Amendment No.

Page 4.4-7 Specification LCO 4.4-1 l l

TABLE 4.4-4 INSTRUMENT OPERATING REQUIREMENTS FOR REACTOR PROTECTIVE SYSTEM, R00 WITHDRAWAL PR0HIBIT (RWP)

MINIMUM MINIMUM PERMISSIBLE

, TRIP OPERABLE DEGREE OF BYPASS NO. FUNCTIONAL UNIT SETTING CHANNELS REDUNDANCY CONDITIONS

1. Startup Channel-Low > 2.5 cps 2 1 Above 10-3%

count rate Rated Power 2a. Linear Channel-Low power RWP -> 5% (m) 2 1 (g)

(Channels 3,4and5) 2b. Linear Channel-Low power RWP > 5% (m) 2 1 (g)

(Channels 6, 7 and 8) 3a. linear Channel-High power RWP (Channels 3, 4 and 5) 1 30%(n) 2(f) 1 None 3b. Linear Channel-High power RWP S 30%(n) 2 (f) 1 None (Channels 6, 7 and 8) l TABLE 4.4-5 l INSTRUMENT OPERATING REQUIREMENTS FOR

, l 480V A.C. ESSENTIAL BUS UNDERVOLTAGE PROTECTION MINIMUM MINIMUM PERMISSIBLE TRIP OPERABLE DEGREE OF BYPASS NO. FUNCTIONAL UNIT SETTING CHANNELS REDUNDANCY CONDITIONS

1. Degraded Voltage (D.G. 396V-436V with 2(e)(f) 1 None Start, Load Shed and a time delay Sequence) of 114 sec.- 126 sec.

2. Loss of Voltage (D.G. 318V-338V with 2(e)(f) 'l None Start, load Shed and CV-2 Relay Sequence) Setting of Time Dial 6

3. Loss of Voltage (Automa+1c) 361V-383V with 2(u)(f) 1 None Throw Over - ATO) CV-2 Relay Setting of Time Dial 6

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. ., j Fort St. Vrain #1 Technical Specifications il Amendment No.

Page 4.4-8 Specification LCO 4.4.1 l NOTES FOR TABLES 4.4-1 THROUGH 4.4-5 (a) See Specification LSSS3.3 for trip setting.

(b) Two thermocouples from each loop, total of four, constitute one channel.

For each channel, two themocouples must be operable in at least one operating loop for that channel to be considered operable.

(c) With one primary coolant high level moisture monitor tripped, trips of either loop primary coolant moisture monitors will cause full scram.

Hence, number of operable channels (1) minus minimum number required '

i to cause scram (0) equals one, the minimum degree of redundancy.

(d) Loss of voltage on 2 of 3 480V A.C. essential busses for no longer than 35 seconds.

(e) One channel monitors each of the three 480V A.C. essential busses.

A channel trip will occur when two of the three bus undervoltage relays comprising that channel operate.

l (f) The inoperable channel must be in the tripped condition, unless the

trip of the channel will cause the protective action to occur.

(g) RWP bypass pemitted if the bypass also causes associated single channel scram.

(h) Pemissible Bypass Conditions:

1. Any circulator buffer seal malfunction.

II. Loop hot reheat header high activity.

III. As stated in LCO 4.9.2 (j) Items la. or Ic. or Id. accompanied by 2a. , 2b. , 2c. , or 2d. on Table 4.4-2 are required for loop 1 shutdown. Items Ib. or Ic. or if. ,

accompanied by 2a., 2b., 2c., or 2d. on Table 4.4-2 are required for loop 2 shutdown.

(k) One operable helium circulator inlet themocouple in an operable loop is required for the channel to be considered operable.

(m) Low Power RWP bistable resets at 4% after reactor power initially exceeds 5%.

(n) Power range RWP bistables automatically reset at 10% after reactor power is decreased from greater than 30%. The RWP may be manually reset between 10% and 30%.

(p) Item 7a. must be accompanied by item 7c. for Loop 1 shutdown.

Item 7b. must be accompanied by item 7c. for Loop 2 shutdown.

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Amendment No.

Page 4.4-9 i l

l Notes for Tables 4.4-1 through 4.4-5 (continued) ,

(r) Separate instrumentation is provided on each circulator for this functional unit. Only the affected helium circulator shall be shut down within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> if the indicated requirements are not met.

(s) Each channel has 2 microphones running in parallel with one ultrasonic amplifier. For the channel to be considered operable, both microphones and the amplifier must be operable.

(t) A primary coolant dew point moisture monitor shall not b'e considered operable unless the following conditions are met:

1) Reactor Power Range Minimum Sample Flow Startup to 2% 1 sec/sec.

Greater than 2% - 5% 5 sec/sec.

Greater than 5% - 20% 15 scc /sec.

Greater than 20% - 35% 30 sec/sec.

Greater than 35% - 100% 50 scc /sec.

2) Minimum flow of item 1) is alarmed in the control room and the alarm is set in accordance with the power ranges specified.

3) The ambient temperatures indicated by both temporary thermocouples mounted on the flow sensors in penetrations B1 and 83 are less than 185'F.

4) Fixed alarms of I sec/sec and 75 sec/sec are operable. '

l @) One channel consists of three undervoltage relays each l monitoring a single phase of a 480V A.C. essential bus. A l channel trip will occur when two of the three bus l undervoltage relays comprising that channel operate.

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. Fort St. Vrain #1 i i Technical Specifications .

Amendment No.

Page 4.4-10 Basis for Specification LC0 4.4.1 The plant protection system automatically initiates protective functions ,

I to prevent established limits from being exceeded. In addition, other protective instrumentation is provided to initiate action which mitigates the consequences of accidents. This specification provides the limiting conditions for operation necessary to preserve the effectiveness of these instrument systems. '

If the minimum operable channels or the minimum degrees of redundancy for each functional unit of a table cannot be met or cannot be bypassed under the stated pennissible bypass conditions, the following actions shall be taken:

For Table 4.4-1, the reactor shall be shut down within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

For Table 4.4-2, the affected loop shall be shut down within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

For Table 4.4-3, the affected helium circulator shall be shut down within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

For Table 4.4-4, the reactor shall be shut down within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

l For Table 4.4-5, the affected 480V A.C. essential bus shall be declared l inoperable, and the appropriate action for that system shall be l followed.

If, within the indicated time limit, the minimum rumber of operable channels and the minimum degree of redundancy can be reestablished, the system is considered normal and no further action needs to be take.

The trip level settings are included in this section of the specifi-cation. The bases for these settings are briefly discussed below.

Additional discussions pertaining to the scram, loop shutdown and circulator trip inputs may be found in Section 7.1 of the FSAR. High moisture instrumentation is discussed in Section 7.3 of the FSAR.

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Fort St. Vrain #1 Technical Specifications -

Amendment No. ,

Page 5.4-1 .

5.4 INSTRUMENTATION AND CONTROL SYSTEMS - SURVEILLANCE AND CALIBRATION REQUIREMENTS Aoplicability Applies to the surveillance and calibration of the reactor protective system and other critical instrumentation and controls.

Objective To assure the operability of the reactor protection system and other critical instrumentation and controls by specifying their surveillance and calibration frequencies.

Specification SR 5.4.1 - Reactor Protective System and Other Criti si Ir;trumentation and Control Checks, Calibrations, and Tests Tha surveillance ar.d calibration tests of the protective l instrumentation shall be as given in Tables 5.4-1 through t

l 5.4-5:

l a) Table 5.4 Minimum Frequencies for checks,  !

l calibrations, and testing of Scram System.

l b) Table 5.4 Minimum Frequencies for checks, calibrations, and testing of Loop Shutdown System.

l c) Table 5.4 Minimum Frequencies for checks, calibrations, and testing of Circulator Trip System.

l d) Table 5.4 Minimum Frequencies for checks, calibrations, and testing of Rod Withdrawal Prohibit System.

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l e) Table 5.4 Minimum Frequencies for checks, l l calibrations, and testing of 480V A.C. Essential Bus i i Undervoltage Protection. l l

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• Fort St. Vrain #1 i

Technical Spscifications t Amsndment No.

Page 5.4-2  ;

l Basis for Specification SR 5.4.1 l

The specified surveillance check and test minimum frequencies

, are based on established industry practice and ogierating experience at conventional and nuclear power plants. The testing is in accordance with the IEEE Criteria for Nuclear Power Plant Protection Systems, and in accordance with accepted industry standards.

Calibration frequency of the instrument channels listed in l Tables 5.4-1, 5.4-2, 5.4-3, 5.4-4, and 5.4-5 are divided into three categories: passive type indicating devices that can be compared with like units on a continuous basis; semiconductor devices and detectors that may drift or lose sensitivity; and on-off sensors which must be tripped by an external source to determine their setpoint. Drift tests by GGA on transducers similar to the reactor pressure transducers (FSAR Section 7.3.3.2) indicate insignificant long term dri f t.

Therefore a once per refueling cycle calibration was selected for passive devices (thermo-couples, pressure transducers, etc.). Devices incorporating semiconductors, particularly amplifiers, will be also calibrated on a once per refueling cycle basis, and any drift in response or bistable setpoint will be discovered from the test program. Drift of electronic apparatus is not the only consideration in determining a calibration frequency; for example, the change in power distribution and loss of detector chamber sensitivity require that the nuclear power range system be calibrated every month.

On-off sensors are calibrated and tested on a once per refueling cycle basis.

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. l Table 51 9-1 MINIMUM FHEQUENCIES r0R CHECKS. CAllBRATIONS. AND TESTING OF CIRCULATOR TRIP SYSTEM

4. Circulator Penetration a. Test M a. Pressure switches actuated by pressure applied. .

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b. Test M b. Pulse test one channel with another channel -

tripped, and verify proper indications. .

c. Ca l i b ra te R b. Known pressure applied at sensor to adjust trip setting. ,

( l 5. Circulator Drain a. Check D a. Comparison of three separate indicators /ci rculator. ,

Pressure-

b. Test M b. Pulse test one channel with another channel '-

tripped and verify proper indications. ,

c. Ca l i b ra te R c. known pressure applied at sensor to adjust trip setting.

6. Ci rculator Seal a. Check D a. Comparison or 3 separate indicators / circulator, ,

Malfunction

b. Test M b. Pulse test one channel with another channel tripped and verify proper indications,

c. Ca l ib ra te R c. Known pressure applied at sensor to adjust ' -

trip setting.

l 7. Ci rculator Trip a. Test R a. Trip steam turbine drives. Ve ri fy wa te r ,,

turbine automatic start. .

NOTE 1: D - Daily when in use M - Monthly R - Once per refueling cycle P - Prior to each start-up if not done previous week I l

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Table 5.h-5 MIM!Mt!M FRj_QM{fiq11S FOR G ECKSmCAllDRAlj0NS. AND TESTING CF 480V A.C. Er.5ENTIAL BUS UNDERVOLIAGE PROTECTION ,

k Channel Desc ri p t ion Function Freauency fil i

Method

1. Degraded Voltage a. Test M a. Functionally test each undervoltage relay and i t '

(D.G. Sta rt, Load channel by applying simulated loss or voltage Shed and Sequence) signal (s); verify alarms and indications.

b. Ca l ib ra te R b. Known voltage applied to relay. Adjust trip point and indications.

2. Loss or Voltage a. Test M a. Functionally test each undervoltage relay and (D.C. Start, Load channel by applying simulated loss or voltage Shed and Sequence) signal (s); verify alarms and indications,

b. Ca l ib ra te R b. Known voltage applied to relay. Adjust trip i point and indications.

3. Loss of Voltage a. Test M a. Functionally test each undervoltage relay and

( Automa t ic Th row channel by applying simulated loss or voltage .

Over - ATO) Si9nal(s); verify alarms and indications, j

b. Ca l ib ra te R b. Known voltage applied to relay. Adjust trip point and indications. f 4

i NOTE 1: M - Monthly 5, R - Once pe r re fue l ing cyc le

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• Fort St. Vrain #1 Technical Specifications -

Amendment No.

l Page 5.4-13 i Specification SR 5.4.2 - Control Room Smoke Detector The control room smoke detectors and alarms will be functionally tested once per year.

Basis for Specification SR 5.4.2 The control room smoke detectors provide for sensing of the smoke in the outlet air ducts from both the control room and the auxiliary electrical room. In the event of any fire or smoke in the control panels, alarms will be initiated.

Specification SR 5.4.3 - Core Region Outlet temoerature Instrumentation 4

The output of two thermocouples measuring each region outlet 4

temperature will be checked daily during power operation. If the indicated temperatures for a region differ by 2175'F, a j calibration shall be made and the faulty thermocouple replaced by an operable thermocouple. The core region outlet thermocouple shall be calibrated once per year during power operation by traversing a calibrated thermocouple along each of the seven coolant thermocouple assemblies.

Basis for Specification 5.4.3 The long-term thermocouple drift is estimated to be s 15*F per year and this drift was included in the measurement uncertainty of 150*F used to establish LCO 4.1.7. With this measurement uncertainty, a root mean square difference of 2 2 75'F would be an indication of a faulty reading. Daily l

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Fort St. Vrain #1 Technical Specifications -

Amendment No.

l Page 5.4-14 i checks and yearly calibrations are considered adequate since the expected drift in calibration is small and has been included in establishing LCO 4.1.7 (See FSAR Section 7.3.3).

I Specification SR 5.4.4 - pCRV Cooling Water System Temperature Scanner - Surveillance Requirement 1

1 PCRV Cooling System temperature scanner readings shall be checked by comparison of representative liner cooling tube thermocouple outputs to their respective subheader 1

temperatures and associated alarms tested once per month '

during power operation.

All thirty-six (36) outist subheader temperature indicator:

shall be calibrated annually. In addition, ninety-seven (97) liner cooling tube outlet thermocouples shall be cali3:ated j annually.

Basis for Specification SR 5.4.4 l

The temperature scanner for the PCRV cooling system provides for continuous temperature monitoring of the outlet water j temperature of each individual liner cooling tube and alarming of high outlet temperatures.

The surveillance interval specified is sufficient to detect any drift in the output of the individual thermocouples or l

scanner electronics to assure the temperature limitations of l the PCRV cooling system are not exceeded.

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Fort St. Vrain #1 2

Technical Specifications -

Amendment No.

l Page 5.4-15 i The ninety-seven (97) thermocouples shall be distributed ameng the thirty-six (36) subheaders so that between 16.7% and 21.5%

of the total in each subheader are calibrated each year.

Thus, the maximum time b'etween calibration of any one thermocouple, or any complete subheader, shall not exceed six (6) years. The overall percentage of thermocouples calibrated J

per year exceeds 18%.

The surveillance interval for calibration, combined with that for checking, assures sufficient accuracy of temperature 4

measurement to adequately protect the PCRV concrete.

Specification 5R 5.4.5 - PCRV Cooling Water Systen. Flow Scanner - Surveillance Requirement A PCRV Cooling System flow scanner readout shall be taken and alarms functionally checked monthly. The scanner and alarms, and six (6) subheader flow meters shall be calibrated annually.

Basis for Specification SR 5.4.5 The flow scanner acts as a backup to the temperature scanner and initiates no automatic protective action, only an alarm.

Because a restriction or a leak in the system would develop over a period of time, the monthly interval for comparing scanner readouts is sufficient to detect any long term change in the system.

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Fort St. Vrain #1 Technical Specifications -

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Amendment No.

l Page 5.4-16 i Specification SR 5.4.6 - Core AP Indicator - Surveillance Requirement The core AP instrumentation shall be calibrated on a once per refueling cycle. interval.

Basis for Specification SR 5.4.6 Core differential pressure is an indication of gross blockage of flow in the core.

Specification SR 5.4.7 - Control Room Temperature -

Surveillance Requirement The control room temperature control thermostat shall be functionally tested monthly and calibrated annually.

Basis for Specification SR 5.4.7 The surveillance interval specified for functional testing and calibration of the control room thermostat will assure its ability to not only control the room temperature as desired,

• but to also indicate the correct room temperature within the accuracy of the instrument.

Specification SR 5.4.8 - Power to Flow Instrumentation -

Surveillance Requirement The power to flow indication shall be verified daily and shall be calibrated once per refueling cycle.

_ 1 Fort St. Vrain #1 l

. . . * - Technical Specifications  ;~ l Amendment No. '

l Page 5.4-17 . ,

1 Basis for Specification SR 5.4.8 The power to flow ratio indication is an indication of the balance between the heat generation and removal within the primary coolant system. A verification of the power to flow indication on a dails basis is adequate to assure the

, instrument is indicating properly. In addition, any change in

reactor power level no matter how small, should produce a change in the power to flow ratio indication'. A lack of response by this instrumentation would be noticed by the 1

operator. Calibration of the instrumentation on a once per refueling cycle basis is acceptable by industry standards for

this type of instrumentation.

Specification SR 5.4.9 - Area and Miscellaneous Process j _ Radiation Monitors - Serve 111ance Requirement The area radiation monitors shall be functionally checked weekly and calibrated annually.

Basis for Specification SR 5.4.9 The surveillance interval specified for functional testing and calibration are adequate to assure the proper operation of 1

these detectors.

Specification SR 5.4.10 - Seismic Instrumentation -

Surveillance Requirement l

The Seismic Instrumentation shall be functionally tested every l

i six months and calibrated every two years.

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. . ... . Technical Specifications i' Amendment No.

l Page 5.4-18 e i

l l Basis for Specification SR 5.4.10 i

The intervals specified for testing and calibration of the Seismic Instrumentation are recommended by the manufacturer to assure the instruments operate as intended.

Specification SR 5.4.11 - PCRV Surface Temperature Indication - Surveillance Recuirement The PCRV surface temperature indicators shall be functionally tested monthly and calibrated annually.

Basis for Specification SR 5.4.11 The PCRV surface temperature indicators provide for continuous monitoring of surface concrete temperatures to assure the proper temperature gredier.t it maintained through the PCRV wall and heads.

The surveillance interval specified is adequate to detect any drift or malfunction of this instrumentation.

Specification SR 5.4.12 - Analytical System Primary Coolant Moisture Instrumentation - Surveillance Requirements The analytical system primary coolant moisture instrumentation shall be calibrated on a once per refueling cycle basis.

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Fort St. Vrain #1

...** Technical Specifications  ;

Amendment No.

l Page 5.4-19 -

Basis for Specification SR 5.4.12 The surveillance interval specified for calibration of this instrumentation will assure the proper operation of these detectors.

Specification SR 5.4.13 - 480 V Switchgear Room Temperature Indication - Surveillance Requirement The 480 V switchgear room temperature indicator and alarm

, shall be functionally tested monthly and calibrated annually.

Basis for Specification SR 5.4.13 The surveillance interval specified for this instrumentation assures its proper operation on a continuous basis.

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ATTACHMENT 3 SIGNIFICANT HAZARDS CONSIDERATIONS l

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• SIGNIFICANT HAZARDS CONSIDERATIONS I. EVALUATION Table 4.4-5 The undervoltage' protection equipment and trip settings proposed as Table 4.4-5 were part of the original modification previously

' reviewed and evaluated by Public Service Company and the Nuclear Regulatory Commission (P-83415 and G-82338). Therefore, the addition of this equipment to the Technical Specifications is not considered to affect the safety evaluations previously performed nor the conclusions which were reached. These requirements more closely conform to the Standard Technical Specifications and will provide assurance that this equipment and the associated setpoints and functions are maintained operable as a limiting condition for plant operation. The action requirement for Table 4.4-5 is consistent with system operation requirements and will

, provide assurance that appropriate actions are taken to maintain safe shutdown functions and capabilities.

Table 5.4-5 The proposed surveillance requirements and schedule are consistent with the requirements for other protective instrumentation and considered adequate to ensure equipment operability and protective actions.

II. CONCLUSION Based on the above evaluation, it is concluded that operation of Fort St. Vrain in accordance with the proposed changes will not (1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the

possibility of a new or different kind of accident from any l accident previously evaluated, or (3) involve a significant i reduction in any margin of safety.

Therefore, these changes will not increase the risk to the health and safety of the public nor do they involve any significant hazards considerations.

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