ML20092H559

From kanterella
Jump to navigation Jump to search
24 Month Operating Cycle Auxiliary Electrical Sys Surveillance Test Extensions
ML20092H559
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 09/20/1994
From: Fredricksen R, Stranovsky G, Wittich W
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20092H520 List:
References
JAF-RPT-ELEC-01, JAF-RPT-ELEC-01547, JAF-RPT-ELEC-1, JAF-RPT-ELEC-1547, NUDOCS 9509210080
Download: ML20092H559 (28)


Text

-- .

24 MONTII OPERATING CYCLE AUXILIARY ELECTRICAL SYSTEM .

' SURVEILLANCE TEST EXTENSIONS o

00hTROLLED JAF-RPT-ELEC-01547 September,1994 Prepared by:

n G. Stranovsky Date 9 O/fb U Sen. Engineer Nuclear O&M

^

/

('#-

Reviewed by: -

W. Wittich Date P' c'o f[

Supervising Engineer Nuclear Operations & Safety Raytion Co Approved by:

~

Date W

R. Fredricksen Director Nuclear O&M pesws,

. 92 DO U 00 33 By2rr - -' P PDR

24 MONTH OPERATING CYCLE AUXILIARY ELECTRICAL SYSTEM .

SURVEILLANCE TEST EXTENSIONS O

TABLE OF CONTENTS I. EXECUTIVE

SUMMARY

3 II. PURPOSE 4 III. SYSTEMS DESCRIPTION 4 IV. EVALUATIONS 6 V. SURVEILLANCE TEST CHANGES 7 VI.

SUMMARY

AND CONCLUSIONS 15 VII. REFERENCES 16 ATTACHMENT A TECHNICAL SPECIFICATION CHANGES 18 2

24 MONTH OPERATING CYCLE AUXILIARY ELECTRICAL SYSTEM SURVEILLANCE TEST EXTENSIONS

^s (G

I. Executive Summary The FitzPatrick plant will be operating on a 24 month fuel cycle. This longer cycle length has a direct effect on surveillance, maintenance, and test activities that are currer.tly performed on a 18 month or refuel outage basis.

This study evaluates the changes to surveillance requirements and proposes Technical Specification changes to support a nominal twenty four month fuel cycle.

Justification is provided, where appropriate, to support test interval extensions.

At FitzPatrick,the Auxiliary Electrical System components are routinely inspected, A tested, and maintained to provide a highly reliable system. Test frequencies are mandated by the plants technical specifications, operational requirements and service inspection schedules.

In addition, preventive maintenance (PM) is periodically performed on individual auxiliary electrical components.

The auxiliary electrical system maintenance activities (PMs) will be reviewed separately to examine the extension of the individual equipment maintenance cycle.

Our evaluations conclude that the auxiliary electrical system surveillance intervals can be safely extended to support a nominal 24 month operating cycle.

4 3

24 MONTH OPERATING CYCLE AUXILIARY ELECTRICAL SYSTEM SURVEILLANCE TEST EXTENSIONS O

II. Pumose The FitzPatrick plant will be operating on a 24 month fuel cycle. To avoid either an 18 - month survaillance outage or an extended mid-cycle outage, changes are required to the auxiliary electrical system surveillance test intervals prescribed by the FitzPatrick Technical Specifications. Substantiating the impacts of the longer cycle length on the auxi.liary electrical system surveillance, maintenance, and test activities require a comprehensive review of the individual electrical systems, its components.

and the integrated effects of all tests and activities on operability.

111. Systems Description The piant electrical power systems include electrical equipment and connections required to generate power and deliver it to the 345kV transmission system. The i p' plant electrical power systems consist of normal, reserve and emergency AC power sources, the Plant Service AC power Distribution System, the 125V DC Power system the 24V DC Power System, and the 600V Motor Operated Valves DC/AC Inverter.

l The emergency AC power source provides AC power to auxiliaries required for l shutdown of the plant in the event that neither the normal nor the reserve power

, source is available. It consists of two independent on site AC generating sources of l power to the emergency buses of the plant service AC power distribution system. l Each of these independent generating sources consist of two diesel generators l operated in parallel. Each source has sufficient capacity to safely shut down the reactor, maintain safe shutdown conditions, and operate all auxiliaries necessary for plant safety.

The emergency AC power sources start automatically upon the following signals:

a. Loss of voltage on an emergency bus (loss of both normal and reserve AC power sources to the plant), with time delay;
b. Degraded voltage on an emergency bus (degraded voltage of both normal and reserve AC power sources) with time delay dependent upon LOCA condition; O c. LOCA (low reactor water level or high drywell pressure).

4

24 MONTH OPERATING CYCLE AUXILIARY ELECTRICAL SYSTEM SURVEILLANCE TEST EXTENSIONS O Individual local and remote controls are provided for manual start and stop of each emergency AC power source. Ren'ote controls are provided for full functional testing of each emergency AC power source.

The 125V DC power system provides two independent on site sources of DC power required for plant startup, operation and shutdown and for supplying all DC loads essential for plant safety. The 125V DC power system is comprised of two separate and independent 125V DC systems each consisting of a battery, a static battery charger, a battry control board, motor control centers, and distribution and lighting paneh The battery chargers normally supply the 125V DC lor 1; while maintaining the batteries at a fully charged state. When a battery charger is out of service or loses AC power, its associated battery will supply the 125V DC loads. The battery chargers are each powered from separate 600V emergency buses.

The 419V DC LPCI power supply system is designed to maintain a reliable power supply during a loss of offsite power coincident with a design basis LOCA. The LPCI independent power supply system provides an independent power source for the operation of three motor operated valves in each of the two redundant RHR-low pressure coolant injection loops and two motor pd operated valves in each of the two Reactor Water Recirculation System loops.

The 419V DC power supply system includes two separate and independent 500kVA uninterruptible power supplies, each consisting of a battery, an inverter, a rectifier / charger, a transformer and associated circuit breakers.

The Reactor Protection System includes two motor-generator power supplies with associated control and indicating equipment sensors, relays, bypass circuitry and switches that cause rapid insertion of control rods to shut down the reactor. The output of each power supply, generator or transformer, is provided with redundant circuit breakers to protect the loads from overvoltage, under-frequency, and undervoltage. These circuit breakers and associated sensing and logic devices make up the eight electrical protection assemblies (EPAs).

V 5

24 MONTH OPERATING CYCLE AUXILIARY ELECTRICAL SYSTEM SURVEILLANCE TEST EXTENSIONS r

i IV. Evaluation Auxiliary electrical system tests and inspection activities were methodically evaluated to determine the impacts of a 24 month operating cycle. Tests and inspections that are currently performed on shorter than 18 month intervals or longer than 30 month intervals were not reviewed because these calibration intervals do not change.

The longer cycle length requires an evaluation of the following "once every refueling" tests:

1) Emergency AC power load sequencing test and 4 kV emergency power system voltage relays instrument functional test.(ST-9C)
2) LOCA bypass of EDG shutdown logic functional test. (ST-9E)
3) EDG Logic system test (ST-9N)
4) Functional Test of Breakers 10514 and 10614 EDG Logic Aux. Stationary Contacts (ST-09P)
5) UPS MG Set Transfer Functional Test (ST-16K)
6) Breaker 10614 Component Operation and Isolation Verification (ST-43H)
7) 125 volt DC station battery service and charger performance test. (MST-71.20)
8) LPCI battery service duty cycle & charger-inverter performance surveillance test.

(MST-71.23)

9) LPCI and LPCI MOV Power Supply Simulated Automatic Actuation Test (ST-2F) Evaluated in the ECCS Mechanical report.
10) Security Door Key Lock Override and Alternate Power Source Check (ST-99)

Addressed in Miscellaneous report.

11) ISP-94 Evaluated in RPS report JAF-RPT-RPS-01324.

p V Surveillance Test Extension Justification: .

6

24 MONTH OPERATING CYCLE AUXILIARY ELECTRICAL SYSTEM SURVEILLANCE TEST EXTENSIONS  ;

The operability of spams and components required by the plant's safety analyses is established by the surveillance requirements contained in the Technical Specifications.

P veillance testing, by definition, can only identify that a component or a system is incapable of performing its safety function (i.e., inoperable). Preventive maintenance, however, reduces the number of failures found during plant operation or during testing.

The decision to extend surveillance test intervals considers:  !

The system's safety function, logic circuitry, instrument loops and individual )

components which accomplish this function.

The effects of testing and maintenance activities on system operability, and the  ;

burden of testing at power were considered. For example; testing that could lead to j a plant transient, testing that results in. unnecessary equipment wear or radiation exposure to plant personnel.

This evaluation included a study of specific surveillance histories, and operational occurrences. Surveillance test data was analyzed, where applicable, for components affected by the extended surveillance interval. Operational occurrence reports (1988-1992) related to the FitzPatrick electrical systems were reviewed, and no significant problems were detected.

1 V. Surveillance Test Chances The following is an evaluation of auxiliary electrical system tests and historical equipment performance for auxiliary electrical system components:

1. Emergency AC Power Load Sequencing Test and 4kV Emergency Power System Voltage Relays Instrument Functional Test (ST-9C):

This once per operating cycle test verifies that each pair of EDGs will start, accelerate, force parallel and accept its emergency loads in the prescribed sequence under conditions that simulate those requiring the EDG system.

Automatic start signals to the EDGs (in pairs) shall be simulated by placing the keylock restart test switch in the Control Room in TEST. EDG starting and breaker and load sequencing shall then be verified. This also satisfactorily tests the operability of the 4kV emergency bus undervoltage relays and timer.

The emergency AC power system voltage relays instrument functional test can, be safely extended with the longer fuel cycle. Potential EDG operability 7

24 MONTH OPERATING CYCLE AUXILIARY ELECTRICAL SYSTEM SURVEILLANCE TEST EXTENSIONS

~

problems can be detected by on-line testing. The monthly EDG Full Load Test verifies the ability of each pair of EDGs to start, accelerate, force parallel, share loads and carry full rated load. The FitzPatrick Technical Specifications also require, during the monthly test, the EDG system instrumentation be checked, the diesel started air compressors be checked for proper operation and their ability to recharge air receivers, and the diesel fuel oil transfer systems be checked for proper operation. The FitzPatrick I Technical Specification require demonstrating the availability of the operable EDGs by manual starting and force paralleling where applicable once within i

one hour and at least once per twenty four hours thereafter while the reactor is being operated with:

1) incoming power available from only one line or through only one reserve I station service transformer,  !
2) incoming power is not available from any line or through either reserve

{

station transformer or i

3) one of the EDGs systems inoperable In addition, this surveillance test can be safely extended to 24 month cycle interval based on the review of the past test data that show the following:

a) The test dated 4/18/87 show the B core spray timer being readjusted prior '

to completing this ST. This means that this portion of the test failed.

b) Tests performed in 1988 and in 1990 passed all portions of the ST.

c) In 1992 the ECCS pump sequencing timer failed the first time, then when retested, passed die test.

d) In 1993 the test passed, however the ECCS pump sequence timers were removed from this procedure and placed to procedures ST-2H and ST-3J. The test methods in the procedures ST-2H and ST-3J were improved by use of electronic timers. Pump sequencing timers may have originally failed due to use of a stopwatch. The calibration frequency in these procedures is once/180 days. Therefore we can safely extend this test to 24 months since the portion of the test that was difficult to pass on 18 month interval was placed on semiannual calibration interval.

l

2. LOCA Bypass of EDG Shutdown Logic Functional Test (ST-9E): l 1

l This once per operating cycle test verifies that low lube oil pressure and high j circulating water temperature will not shut down the EDG when started in an '

accident condition. With EDG running, an EDG shutdown logic circuit lead p %

will be lifted to simulate LOCA signals. Low inbe oil pressure switch and high jacket water temperature switch contacts will be jumpered to simulate, engine shutdown signals. Continued EDG operation will demonstrate LOCA 8 l l

l

24 MONTH OPERATING CYCLE AUXILIARY ELECTRICAL SYSTEM SURVEILLANCE TEST EXTENSIONS h bypass of these shutdown signals. When both LOCA relays have been tested, the lifted lead will be installed with the shutdown signal still applied, demonstrating proper shutdown logic function.

The LOCA bypass of EDG shutdown logic functional test can be safely extended to 24 month cycle interval because the review of the surveillance tests performed in 4/18/87,12/1/91/,1/27/93 and 2/5/93 show that the test was satisfactory and no corrective action was required. Once the logic system is wired correctly, unless there is a component failure, the logic should work regardless of testing it once per 18 or 24 months.

3. EDG Logic System Test (ST-9N)

This test demonstrates the operability of the following:

a) Auto start on degraded bus voltage with and without LOCA signal. This is accomplished by simulating the associated signal and verifying the EDG logic is satisfied. Actual start is prevented by placing the EDGs in the maintenance mode.

O b) Auto start on a LOCA signal. This is accomplished by simulating the V associated signal and verifying the EDG starting logic is satisfied, as it is done for degraded bus voltage auto start.

c) Emergency 4.16 kV bus load shedding. This is accomplished by operating the associated pumps, initiating load shed signal, and verifying pump trips.

d)LOCA signal bypass of EDG auto-shutdown due to high jacket water temperature or low lube oil pressure. This is accomplished by using jumpers, and verifying the status by observing the status of the EDG shutdown relay and local and remote annunciators.

The EDG Logic System Test can be safely extended to 24 month cycle interval for the following reasons:

This test is a result of OER of NRC Information Notice 91-13, which resulted in LER 050-00, Inadequate Testing of EDGs. On 11/11/92 while we were in a shutdown mode it was found that while the Instmment Surveillance Procedures did test all required relays, there was inadequate testing of the complete circuits to ensure that a component failure did not exist. The test was performed on 4/28/94 and acceptance criteria was satisfied.

The extension of the surveillance interval from 18 to 24 months should have a negligible effect on the reliability of this system, since the diesel generator logic has been functional from the original plant start up. In addition, ISP-90 s and 91 provide overlap testing to ensure operability of the undervoltage, circuitry.

9

24 MONTH OPERATING CYCLE AUXILIARY ELECTRICAL SYSTEM SURVEILLANCE TEST EXTENSIONS A

V

4. Functional Test of Breakers 10514 and 10614 EDG Logic Auxiliary Stationary Contacts (ST-P).

This test demonstrates the operability of auxiliary contacts of breakers 10514 and 10614 used in the load shedding and undervoltage operation. Breakers 10514 and 1%14 tie the emergency buses with the normal 4.16 KV source fed from the normal T-4 or startup transformers T-2 or T-3. Diesel generator A is used for testing breaker 10514 aux. contacts and diesel generator D is used to test the contacts of the breaker 10614. The test for both breakers are the same, the following steps are for breaker 10514:

a) Verify no continuity or minimum voltage drop between points across contacts tested.

b) Synchronize DG-A to bus 10500, closing breaker 10502.

c) Assume load from DG-A.

d) Open bus tie breaker 10514.

e) Verify continuity or voltage drop between points across contacts tested.

f) Synchronize buses 10500 and 10300 and close tie breaker 10514.

g) Unload DG-A, trip breaker 10502.

I h) Verify no continuity or minimum voltage drop between points across contacts tested.

This test can be safely extended for longer fuel cycle for the following reasons:

This test is a result of an LER 050-00, (ref.28) Inadequate Testing of Diesel Generators. On 11/11/92 it was found that whP.e the instrutnent Surveillance Procedures did test all of the required relays, there was inadequate testing of the complete circuits to ensure that a component failure did not exist. Auxiliary contacts of these breakers were previously not tested.

Since this is relatively new test procedure, we do not have past data for review. However, results of the test completed on 4/25/94 show that the acceptance criteria was satisfied.

p The extension of the surveillance cycle should have a minimal effect on the reliability of this system.

4 10

24 MONTH OPERATING CYCLE AUXILIARY ELECTRICAL SYSTEM SURVEILLANCE TEST EXTENSIONS

5. UPS MG Set Transfer Functional Test ST-16K.

The UPS system consists of AC and DC motor generator combination to generate vital single phase 120 V AC power source. The AC motor is 575 V, DC source is our station 125V DC battery.

With the UPS MG set running on AC drive, the AC drive motor is tripped by opening the AC feeder breaker to the UPS MG set. This causes the MG wi to transfer from AC drive to DC drive without an interruption of power to the UPS bus.

The DC drive motor is tripped by depressing the UPS MG set Stop pushbutton. This will result in an interrupted transfer of the UPS bus from the generator output to alternate 120 V AC feeder.

The final step is to test the UPS bus transfer from the alternate feeder to UPS MG AC drive.

This test was instituted after Nine Mile #2 Plants UPS failure in 1991. It was found, that the problem at NM-2 was unique, we do have a different UPS manufacturer, however, we did not perform specific surveillance tests for UPS.

This test can be safely extended to 24 month fuel cycle interval. Surveillance

(]'

\ tests performed on 7/7/92 and 4/12/94 were satisfactory with no corrective action required. A review of the past work orders for this system shows that we do not have problems with the UPS system.

6. Breaker 10614 Component Operation and Isolation Verification ST-43H.

The purpose of this test is to demonstrate the circuit breaker 10614 local and remote operation. Circuit breaker 10614 ties emergency bus 10600 with normal or startup 4.16 KV source. The " Local" " Remote" switch is located on remote shutdown panel 25 ASP-3.

Placing the control switch in Local position, we check that the control and indication is available on panel 25 ASP-3 and indication is not available at Control Room panel 09-8. Reverse is true when the control switch is placed in Remote position.

This test can be safely extended to 24 month fuel cycle interval. Once the Control Room and Remote Shutdown panel was wired up correctly and tested, then this function is not time dependent. Test result from 4/26/94 show successful test, no corrective action required.

O 7. 125V DC Station Battery Service and Charger Performance Test (MST-71.20).

11

24 MONTH OPERATING CYCLE AUXILIARY ELECTRICAL SYSTEM SURVEILLANCE TEST EXTENSIONS The 125V DC system is comprised of two separate and independent 125V DC power sources. Each power source consists of a pasted plate, lead calcium, 58 cell battery and its static charger. Normal 125V DC loads are supplied by the battery chargers.

IEEE 450-1987 (Reference ) provides recommended maintenance practices and testing procedures that can be used to optimize the life and performance of large lead storage batteries. It also provides guidance for determining when batteries should be replaced. IEEE 450-1987 endorses the following types of capacity tests for evaluating battery capability:

Performance Test: This is a constant current capacity test made on a battery normally in the "as-found" condition, after being in service to detect any change in the battery capacity which would indicate degradation.

Service Test (Duty Cycle Test): A special battery capacity test which may be required to determine if the battery can meet the design requirements (battery duty cycle) of the DC system.

In general, IEEE 450-1987 recommends that a performance test of the battery capacity be made within the first two years of service and then at 5 year r intervals until it shows signs of degradation. No surveillance frequency is i

specified for the service test.

The " refueling interval" station battery service and charger performance test (MST-071.20 ) verifies the 125V DC station batteries' ability to satisfy the design requirements of the battery duty cycle and to test the ability of the 125V DC station battery charger to recharge the battery after the service discharge test. This test is required by the Technical Specifications and is performed in accordance with IEEE 450-1987. In this test, the prescribed design load cycle is applied to the battery and the appropriate voltage and current measurements are recorded. Following the service test, the ability of the battery charger to recharge the battery is tested. Battery charger current and voltage are measured and recorded during the recharging period. The battery is then put on an equalizing charge.

The Tech Specs also require a performance discharge test of the batteries (MST-071.21) at 5 year intervals. This test verifies that battery capacity is not below the design requirements, and contains a provision to test the batteries on an accelerated schedule if battery capacity is less than or equal to 85% or has dropped more than 10% from its capacity on the previous performance test.

The 125V DC station battery service test and charger performance test can be O safely extended with the longer fuel cycle. Potential station battery and, charger operability problems would be detected by the following combination 12

24 MONTH OPERATING CYCLE AUXILIARY ELECTRICAL SYSTEM SURVEILLANCE TEST EXTENSIONS of on-line tests and inspections:

  • Every week the specific gravity, voltage and temperature of the pilot cell and overall battery voltage is measured (MST-71.12 ). The 125V DC system is also visually inspected for: a) battery and battery area clean, b) no cracked cells nor electrolyte leakage, c) any evidence of  ;

corrosion at either terminals or connectors, d) electrolyte level within the level markings on the jars, and e) battery charger current and voltage output.

  • The quarterly station battery surveillance test (MST-71.13) measures:

a) the voltage of each cell to the nearest 0.0lv, b) specific gravity of each cell, and c) temperature of every fifth cell. In addition, a comprehensive visual inspection is performed and an equalizing charge is applied if necessary.

  • Each year, various maintenance tasks are performed on the station batteries and other stationary batteries throughout the plant (MP-57.6).

This annual maintenance activity includes cell cleaning, verifying cell connections (through measurement of intercell connection resistance),

individual cell charging, electrolyte concentration adjustments, battery rack maintenance, and replacing cells if necessary.

Thus, adequate on-line surveillance testing and maintenance programs are in place to ensure that the station batteries and their associated chargers are functioning properly. This extensive on-line testing program establishes the operability of the batteries while the refueling test demonstrates the battery's ability to meet the design requirements of the system.

During the test performed on June 10, 1991 one charger supply breaker tripped on overcurrent during recharge of station battery A. Investigation of this problem revealed that the battery charger was operating within its specified limits. The 90 Amp feeder breaker and the corresponding cable however were determined to be undersized for the charger current limit rating  !

(JSEM-91-0042). It was concluded that this problem did not have an adverse effect on availability of the 125V DC system. A review of test results for the past five years shows no other problems were identified during the service test. j The 125V DC station battery service and charger operability surveillance test can be safely extended to 24 month operating cycle because:

1) Service and performance testing of battery capability is in accordance with A the recommendations of IEEE 450-1987 U 2) On-line testing provides adequate assurances that station battery and, charger operability problems would be detected through the weekly, quarterly 13 l

1

24 MONTH OPERATING CYCLE AUXILIARY ELECTRICAL SYSTEM l SURVEILLANCE TEST EXTENSIONS I

and annual surveillances.

3) A review of past tests completed on 11/9/93,11/18/93 and 4/18/94 show l that they were satisfactory. l
4) Computer trending of the cells gravity will indicate if we have potential l problems tvith the battery.
8. LPCI Battery Duty Cycle & Charger-Inverter Performance Surveillance Test MST-071.23.

The test demonstrates operability of the LIPCI battery by performance of a duty cycle test. It consists of as found data collection of battery voltages, battery isolation from inverter and charger and separate battery into three separate segments due to test equipment limitations. Discharge test equipment is connected to the battery for the service test. The service test measures the battery voltage to verify that it does not decrease below minimum acceptable required value. The test is repeated for each battery segment. Following the test equipment disconnection, the battery is connected to inverter for the inverter performance test.

The inverter performance test demonstrates the operability of the independent power supply to supply power under simulated accident conditions. Inverter is tripped simulating low voltage conditions, charger is taken off line and motor operated valves are stroked. Electrical parameters are monitored. At the end, the inverter is placed back on line and battery is recharged.

The test results for battery B are as follows:

2/8/92 - unsatisfactory. Cell no 57 failed and was replaced.

8/12/92 - unsatisfactory. Service portion of this procedure failed to meet the acceptance requirement (ICV dropped below 1.75 V per cell). The inverter portion of the test failed due to test equipment failure. (recorder failed) 9/3/92 - satisfactory 10/30/93 - unsatisfactory. Subsequently the test procedure was revised to change the discharge rates and times to more closely coincide with those of JAF-CALC-ELEC-00562.

11/1/93 - satisfactory 11/3/93 - satisfactory For battery A:

9/19/92 - satisfactory 4/22/94 - satisfactory. Gravity readings of cells 29 and 118 were lower than action limit. Maintenance instituted trending and the cells gravity is acceptable.

14

__]

24 MONTH OPERATING CYCLE AUXILIARY ELECTRICAL SYSTEM SURVEILLANCE TEST EXTENSIONS O This test cen be sefeir extended to 24 month cvcie intervei for the feiiewies reasons:

1) Service and performance testing is done in accordance with the recommendations of IEEE 450-1987.
2) The battery is tested weekly and quarterly (MST-71.10 and MST-71.11) to detect any operability problems.
3) The review of the past test results show that while we had problems passing this test due to test equipment failure, incorrect acceptance criteria, the actual performance and duty cycle test did not cause the test to be unsatisfactory. 4) Computer trending of the gravity of the individual cells should indicate potential problems with the battery.

VI. Summary and Conclusions To support the 24 month fuel cycle, extension of the once per operating cycle auxiliary electrical system surveillance test intervals and maintenance surveillance test procedures is proposed.

p Surveillance tests: ST-9C, ST-9E, ST-9N, ST-P, ST-16K, ST-43H, MST-71.20 and MST-71.23 can safely be extended to 24 month cycle.

Technical Specification changes are required to indicate that the test frequency is extended to maximum of 30 months. (24 months +-6 months) Attachment A shows all proposed Technical Specification changes.

The changes, which extend the test intervals, do not involve an unreviewed safety question nor do they constitute a Significant Hazards Consideration. Extended surveillance intervals do not increase the probability of an accident occurring, and consequences of an accident. However, increasing the surveillance intervals may affect the probability of equipment malfunction.

Based on the individual surveillance test review, the probability of occurrence and the consequences of an accident or malfunction of safety related equipment previously evaluated in the safety analysis report will not be increased.

The possibility of an accident or malfunction of a different type than evaluated previously in the safety analysis report is not created. The proposed changes do not create any new failure modes or a new accidents.

The margin of safety as defined in the basis for any technical specification is not reduced. The proposed changes extend surveillance intervals. Evaluation of past Ox performance of the equipment indicates that the effect of extending the surveillance tests would not involve a significant reduction in a margin of safety.

15

24 MONTH OPERATING CYCLE AUXILIARY ELECTRICAL SYSTEM SURVEILLANCE TEST EXTENSIONS O

VII. References ,

l l

1. James A. FitzPatrick Nuclear Power Plant, Surveillance Test Data Index dated 5/2/94. ,
2. James A. FitzPatrick Nuclear Power Plant, Index of Operations Surveillance Test Procedures dated 4/29/94.  ;
3. Data sheets from 1986 to 1990 for the following surveillance tests: l l

I

4. Operational Occurrence Report Logs from 1986 to 1990.
5. Operation Surveillance Test Procedure No. 2F, "LPCI & LPCI MOV Power Supply Simulated Automatic Actuation Test
6. Operations Surveillance Test Procedure No. 9B, "EDG Full Load Test and ESW Pump Operability Test," Revision 32, dated February 13, 1991.

pv 7. Operations Surveillance Test Procedure No. 9C, " Emergency AC Power Load Sequencing Test and 4 kV Emergency Power System Voltage Relays Instrument Functional Test," Revision 9, dated June 6,1990.

8. Operations Surveillance Test Procedure No. 9D, "EDG,115 kV Reserve Power Station Battery or ESW Pump Inoperable Test," Revision 16, dated April 4,1991.
9. Operations Surveillance Test Procedure No. 9E, "LOCA Bypass of EDG Shutdown Logic Functional Test," hevision 2, dated November 14, 1990.
10. Operations Surveillance Test Procedure ST-09N.
11. Operations Survbillance Test Procedure ST-09P.
12. Maintenance Surveillance Test Procedure ST-16K.
13. Maintenance Surveillance Test Procedure ST-29B.
14. Maintenance Surveillance Test Procedure ST-43H.
15. Maintenance Surveillance Test Procedure ST-99.
16. Maintenance Surveillance Test Procedure MST-071.20, "125VDC Station Battery Service and Charger Performance Test. ,

16

24 MONTH OPERATING CYCLE AUXILIARY ELECTRICAL SYSTEM SURVEILLANCF, TEST EXTENSIONS

17. Maintenance Surveillance Test Procedure MST-071.21, Station Battery Performance Test.
18. Maintenance Surveillance Test Procedure MST-071.22, "LPCI Battery Performance Test".
19. Maintenance Surveillance Test Procedure MST-071.23.
20. Operating Procedure No. F-OP-43A, "125V DC Power System," Revision 9, dated  :

June 21,1991.

21. Operating Procedure No. OP-43C, "LPCI Independent Power Supply System,"

Revision 5, dated April 6,1991.

22. ISA-S67.04-1982 "Setpoints for Nuclear Safety Related Instrumentation Used in Nuclear Power Plants."  !
23. USNRC Reg. Guide 1.105 " Instrument Setpoints for Safety Related Systems,"

Revision 2, dated February 1986.

24. James A. FitzPatrick Nuclear Power Plant, Technical Specifications Sections 3.9 and O 4.9.

U

25. James A. FitzPatrick Nuclear Power Plant, Updated Final Safety Analysis Report, Section 8.2.
26. IEEE 450-1987.
27. LER: 92-050 Inadequate Testing of Emergency Diesel Generators, dated 12/9/92.

O .

ATTACHMENT A 17

. v

~

24 MONTH OPERATING CYCLE AUXILIARY ELECTRICAL SYSTEM -

SURVEILLANCE TEST EXTENSIONS

-O ATTACHMENT A TECHNICAL SPECIFICATION CHANGES O

P 0

4 4

O. i i

i 18

O a*Fuee O 3 O

ont'd) 4.9 (cont'd) 3' From and after the time that both batteries are made or 3. Once each not to exce ths the found to be inoperable for any reason, the reactor shall be sta batteries snalt be subjected to a ervice (duty in a cold condition within 24 hrs. '
4. Once each 5 year interval the station batteries shall be subjected to a performance discharge (capacity) test.. l S. Each battery charger shall be visually inspected weekly

'and a performance test conducted each operating cycle

. not to exceed 18 months.

G. Once/ month: open 16elhlfer~y charger output breakers one at a time and observa performance for propcr

] operation.

I e e

~[O e

\

7 h

odrnent No. 167 m

'  ?

n .

JAFNPP V O

ont'd) 4.9 (cont *d)

LPCI MOV Independent Power Supplies F. LPCI MOV Independent Power Supplies I

1. Every week the specific gravity, voltage and temperature of each pilot cell, and overall battery voltage shall be measured and chargers and inverters shall be visually inspected.
2. Every three months the following measurements shall be made
a. Voltage of each cell to the nearest of 0.01v;
b. Specific gravity of each cell;
c. Temperature of every fifth cell. [y

, 3. Once each ating cycle to ex ths the battery shall be 'ected to a sennce (duty cycle) test. 8

4. Once each 5-year interval the battery shall be subjected to a performance discharge (capacity) test.
5. Each battery charger and inverter shall be visually inspectadyrocisly_ mod a .rwinrm7 test conducted each operating cycle not to ex 8 hs. ,
6. Once mornn. open the battery ch A.C input breakers one at a time and observe perfor for proper operation.

? ment No.MXJ8f 167 222a L

o o O JAFNPP u gy(( fER lif [f 0N0lS " ,

4.9 BASES Once per month tests are conducted for support systems The general objective of this specification is to check equipment independently or as part of monthly diesel generator opercbility, detect equipment failures and deterioration. surveillance: (a) to check the air starting systems for automatic starting of the compressors and their ability to A. Normal and fleserve A-C Power Systems recharge the receivers. Ib) to check the fuel oil transfer system to ensure that the transfer pumps will refill the day

1. Reserve A-C Power Source tanks.

The equipment is normally operated in the stand-by During the operating cycle test, functional test of the energized condition. Surveillance monitors are provided emergency a-c power system is made by simulating a for determining its normal operability status both while in loss-of-coolant accident and a coincident loss of normal stand-by or during plant startup and shutdown and reserve a-c power to the plant for checking proper procedures. Insulation tests are conducted at specified operation of the system including sequencing of intervals to determine the condition of insulation. engineered safeguards and for Emergency Core Cooling System equipment.

2. Auxiliary Equipment C. Diesel Fuel-Mechanical and electrical tests are conducted at specified intervals to assure proper functioning of Diesel fuel quality is checked at specified intervals to equipment. ensure high reliability of engine operation. l B. Emeroency A-C Power System The operability of the fuel oil transfer system is demonstrated by partially draining the day tanks, initiating The emergency Diesel Generatoc Systems are tested monthly low and low-low level signals to start the lead and backup to dotermine functional performance. Test procedures and pumps, respectively, and terminating f uel oil transfer on a intervals are specified to check for failure or deterioration in high level signal.

equipment and system operation since fast use. Full load applied to the diesel unit is applied to prevent fouling of the engine: operation at equilibrium temperatures ensures there are no overheat problems.

Amendment No. 205  ??S

~ J

  • new sumruvm O - IP3 Autho 10 CFR 50.59 NUCLEAR SAFETY EVALUATIO'N Form F- ,a-JAF

, Number: m E- W- / 2 O Revision: /

tivity: O Modification O Procedt:re GT Test O Experiment O Other ivity Number: fT)CT C / . M- t'd ,[/T'57- C/. d5 - RI / MG7- M1,2$C

Title:

STATut) /9//D L PC / 8 At/i e y' rt' O D i W D P5l'FtW Arin TE~sT~i A. The proposed activity

1. Odoes gdoes not increase the probability of occurrence of an accident eva!uated .

in the safety analysis report.

~

2. Odoes Edoes not increase the consequences of an accident evaluated previously in the safety analysis report.
3. Odoes Edoes not increase the probabiltty of occurrence of a malfunction of equipment important to safety evaluated previously in the safety analysis report.
4. Odoes Edoes not increase the consequence of a malfunction of equipment important to safety evaluated previously in the safety analysis report.
5. Odoes gdoes not create the possibility of an accident of a different type than any evaluated previously in the safety analysis report
6. Odoes Edoes not create the possibility of a matfunction of equipment important to safety of a different type than any evaluated previously in the safety analysis report.

I 7. Odoes ,$does not reduce the margin of safety as defined in the basis of any Technical l l Specification.

B. Odoes Rdoes not involve an unreviewed safety question based on questions 1 through 7.

9. Odoes %does not degrade the Secunty Plan. Quatrty Assurance Program or the Fire l Protection System.

B. The proposed activity

1. Odoes Mdo[s not require a change to the Final Safety Analysis Report as indicated in Section l 3 of this Nuclear Safety Evaluation (NSE).
2. Odoes Kdoccnot require action tracking of the items indicated in Section 5 of this NSE.

C. This proposed activity. l

1. Odoes @does not require a change to the Technical Specifications.
2. Odoes Edoes not require an Environmental Impact Evaluation.
3. Odoes ETdoes not require a change to Design Basis Documents.

Prepared by: - [. (M Date: / '

" Date:

Reviewed by '

"~ E Date:

i r~N Recommended: AppropL[ Disyproval h PORC Mts -

Approved by- /NT. t. / Da;.e: / '

Resident Mgr. or[esign9e7 Distnbution: SRC Coordinator. JAF Site Eng Mgr/IP3 Technral Services Mgr (annual 50.59 report) RMSJAF/IP3 NYPA FORM MCM4. ATTACHMENT 4 3 Page 1 of 1

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT NUCLEAR SAFETY EVALUATION

()

Purpose:

JAF-SE-94-120, REV. 1 I.

This safety evaluation documents the acceptability of the proposed alternate battery test method described in MST-071.24, MST-071.26 and MST-071.25 to be performed on the l Station and LPCI BP ' eries respectively. These procedures may be used when botn the battery service and performance tests are required to be performed consecutively. This testing method allows a single modified performance test to be utilized which meets the JAF Technical Specification requirements for both tests by ensuring that the batteries are capable of supplying the design basis duty cycle loads and by performing a performance test (discharge test) to determine battery capacity and provide trendable data. The implementation of this cingle test increases the availability of the respective batteries because of the reduced time required for testing and charging, provided acceptance criteria is met. Each of the Station and LPCI Batteries requires a Service test once per cycle not to exceed 18 months and a performance test once each 5 year interval. Battery testing is performed within the guidelines of the IEEE 450-1987 standard. Evaluations (Reference 11. and 12.) have been performed to verify that the modified performance tests meet the testing requirements

(')S

(_ of the individual service and performance tests and are more conservative than either of the individual tests.

II. Description of Proposed Activity:

Service and performance tests are performed on the Station and LPCI Batteries as required by JAF Technical Specifications. The service tests assure that the as-found condition of those batteries satisfy the design battery duty cycle requirements. The existing performance tests trend the change in battery capacity by testing the battery after scheduled maintenance has been completed.

The proposed modified performance test will encompass the requirements of both the service and performance tests by including the peak discharge currents of the battery duty cycle and a constant discharge rate that envelopes the duty cycle for the remainder of the discharge. Two separate acceptance criteria are established for successful service and performance test requirements. The technical basis for the acceptance criteria is obtained from the existing battery service and performance test requirements. Any l differences are conservative and documented in reference 12.

The testing guidelines in IEEE 450-1987 address the initial conditions required when a performance test is performed in

() lieu of a service test. These guidelines are met by the proposed alternate test methods described in MST-071.24, MST-071.26 and MST-071-25.

Page 1 of 6

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT NUCLEAR SAFETY EVALUATION JAF-SE-94-120, REV. 1 o]

/"

III. SAR Review:

Applicable sections of the UFSAR chapters 8.7 and 8.10 were reviewed and no changes were required to address the proposed modified performance tests. The proposed tests do not involve any changes in the Technical Specification Sections 3.9.E, 3.9.F, 4.9.E, or 4.9.F since these tests meet the test requirements for the individual service and performance tests of the Station and LPCI Batteries and meet the testing guidelines specified within the IEEE Std. 450-1987.

IV. Review and An-lvsis:

The MST-071.24, MST-071.25, and MST-071.26, modified l performance tests encompass the service test requirements by including the peak discharge currents of the battery duty cycle and a discharge rate which envelopes the service test discharge rate. The modified performance test utilizes the as-found battery condition because the service test criteria of this test requires that no equalizing charge be performed within 7 days and no battery pre-conditioning

() (cleaning / tightening of the battery connections) be performed prior to testing. For this reason and because the discharge current peaks are included in the normal discharge rate, the rated capacity of the batteries will trend slightly lower than previous performance tests when battery pre-conditioning was performed. Acceptance criteria provided in the proposed tests are based on the acceptance criteria of both the service and performance tests. Any differences are conservative and documented in reference 12.

The Station Battery duty cycle has been revised by JAF-CALC-ELEC-01417 and JAF-CALC-ELEC-01418 which superscedes the 87-B01 Station Battery duty cycle calc.

The JAF Technical Specifications require performance testing of the Station and LPCI Battery Chargers (and LPCI inverters) to be performed once per operating cycle not to exceed 18 months. Charger performance testing is not part of the battery testing requirements but is included in the battery service test procedures. Since the proposed test procedures are provided as alternate test methods for performing both the battery service and performance tests, this same charger acceptance criteria is incorporated in the proposed tests to meet the JAF Technical Specification charger requirements. Portions of the acceptance criteria

~'N for the LPCI charger however, remain and will be performed (d

\

by Reference 7. ,

Page 2 of 6

-- -. - . . . ._- - . _ ~ - . - . _ - . _ _ - .- -- - .=

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT NUCLEAR SAFETY EVALUATION JAF-SE-94-120, REV. 1 IV. Review and Analysis: (continued)

Performing MST-071.24, MST-071.26 and MST-071.25 as l alternatives to performing individual service and performance tests of the Station and LPCI Batteries is acceptable because:

a. The test methods and acceptance criteria for the proposed tests are designed such that they encompass the requirements of the separate existing battery service and performance tests. The battery equipment configuration and required plant conditions during the proposed test are equivalent to the specified configuration and required plant conditions of the existing battery test procedures already approved therefore they do not l'ncrease the probability of occurrence of an accident evaluated in the safety analysis report.
b. For the same reason as (a.) above, the proposed modified performance tests do not increase the consequences of an accident evaluated previously in the safety analysis report.

O c. For the same reason as (a.) above and since the batteries are tested within the constraints of the manufacturer's discharge curves, the proposed modified performance tests do not increase the probability of occurrence of a malfunction of equipment important to safety evaluated previously in the safety analysis report.

I

d. For the same reason as (a.) above, the proposed  !

modified performance tests do not increase the consequences of a malfunction of equipment important to safety evaluated previously in the safety analysis report.

e. For the same reason as (a.) above, the proposed modified performance tests do not create the possibility of an accident of a different type than any evaluated previously in the safety analysis report.
f. For the same reason as (c.) above, the proposed modified performance tests do not create the i possibility of a malfunction of equipment important to I safety of a different type than any evaluated previously in the safety analysis report.

O Page 3 of 6

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT NUCLEAR SAFETY EVALUATION "T JAF-SE-94-120, REV. 1 (G

IV. Review and Analysis:(continued)

g. The proposed modified performance test methods result in more conservative testing criteria than is implemented by the individual service or performance tests therefore they do not reduce the margin of safety as defined in the basis for JAF Technical Specifications,
h. These proposed test procedures do not involve an unreviewed safety question based on questions (a.)

through (g.).

i. The proposed tests do not degrade the Security Plan, Quality Assurance Program or the Fire Protection System because the battery equipment configuration and required plant conditions during the proposed test are equivalent to the specified configuration and required plant conditions of the existing battery test procedures already approved.

- V. Actions Items to be Tracke4: None i

VI gummary of Activity and Nuclear Safety Evaluation:

The MST-071.24 Rev 2, MST-071.26 Rev 0, and MST-071.25 Rev 1 l modified performance tests for the Station and LPCI Batteries may be used as an alternative test method to i performing separate consecutive service and performance tests for these batteries.

The battery equipment configuration and required plant conditions during the proposed test are equivalent or conservative to the specified configuration and required plant conditions of the existing battery test p ocedures.

The conservative differences are documented in reference 12.

The proposed test procedures direct testing of the Station and LPCI batteries to be performed within the constraints of the manufacturer's battery discharge curves.

The Technical Specification test requirements are met because the modified performance tests encompass the service and performance test requirements of the Station and LPCI Batteries and are more conservative than the individual service and performance tests.

A b

Page 4 of 6

\

_ _ _ _ _ _ _ _ _ _ _______ _ ____j

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT NUCLEAR SAFETY EVALUATION JAF-SE-94-120, REV. 1 O

VI Summary of Activity and Nuclear Safety Evaluation:

Based on the above statements, the proposed tests; a) do not increase the probability of occurrence of an accident evaluated in the safety analysis report.

b) do not increase the consequences of an accident evaluated previously in the safety analysis report.

c) do not increase the probability of occurrence of a malfunction of equipment important to safety evaluated previously in the safety analysis report.

d) do not increase the consequences of a malfunction of equipment important to safety evaluated previously in the safety analysis report.

I e) do not create the possibility of an accident of a different type than any evaluated previously in the safety analysis report.

f) do not create the possibility of a malfunction of

() equipment important to safety of a different type than any evaluated previously in the safety analysis report.

g) do not reduce the margin of safety as defined in the basis for JAF Technical Specifications.

VII.

References:

1. UFSAR Section 8.7, 125 VDC Power System
2. UFSAR Section 8.10, 419 VDC LPCI Independent Power Supply System
3. JAFNPP Technical Specifications 3.9.E, 4.9.E, 3.9.F, 4.9.F
4. MST-071.20 R10 125 VDC Station Battery Service and l Charger Performance Test i
5. MST-071.21 R4 125 VDC Station Battery Performance Test l l
6. MST-071.22 R2 LPCI Battery Performance Test
7. MST-071.23 R6 LPCI Battery Duty Cycle and Charger- l Inverter Performance Test Page 5 of 6

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT NUCLEAR SAFETY EVALUA's fON I JAF-SE-94-120, REV. 1 ,

(  :

VII. References (Continued) *

8. IEEE Std. 450-1987 IEEE Recommended Practice for '

Maintenance Testing of Large Lead Storage Batteries for Generating

/

Stations

9. OP-43A, 125 VDC Power System j
10. OP-43C, LPCI Independent Power Supply System
11. Memorandum NED-KN-94-295, Battery Modified Performance Testing
12. Memorandum JMD-94-494, MST-71.24 and MST-71.25, dated ,

Nov. 9, 1994

13. JAF-CALC-ELEC-01417 Rev. 0 125V DC Power System A Sizing
14. JAF-CALC-ELEC-01418 Rev. 0 125V DC Power System B Sizing O

O ,

Page 6 of 6