JPN-91-060, Forwards Response to Generic Ltr 91-06, Resolution of Generic Issue A-30, 'Adequacy of Safety-Related DC Power Supplies.' Advises That Design,Maint,Surveillance & Test Procedures for Dc Power Supplies Reasonable Alternatives
| ML20079L370 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 10/28/1991 |
| From: | Ralph Beedle POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| REF-GTECI-A-30, REF-GTECI-EL, TASK-A-30, TASK-OR GL-91-06, GL-91-6, IPN-91-039, IPN-91-39, JPN-91-060, JPN-91-60, NUDOCS 9111060240 | |
| Download: ML20079L370 (22) | |
Text
{{#Wiki_filter:- - , . . - , 123 Main Stoo M
-' WNte Plains, New York 13fC1
, ,
- 914 681 6846
.4 NewYorkPower n., - ,,.... - tv Authority " - ~ ~
nuo u cene w n October 28,1991 IPN 91-039 JPN 91060 , l U.S. Nuthcr Regulatory Commission ATTN: DocumentControlDesk Mail Station P1137 l Washington, DC 20555
- Subjec': Indian Point 3 Nuclear Power Plant Dockct No.50 286 James A. RtzPatrick Nuclear Power Plant Docket No. 50-333 Response to Generic Letter 91-06 Reformen: U.S. Nuclear Regulatory Commission Generic Letter 91-06, dated April 29,1991, entitled
- Resolution of Generic issue A-30,' Adequacy of Safety Related DC Power Supplies,' Pursuant to 10 CFR 50.54(f).*
Dear Str. Generic Letter 91-06 asked licensees to complete a questionnaire about the DC power supplies installert in their plants. Enclosures I and 11 are the completed questionrnires for the Indian Point and RtzPatrick Nuclear Power Plants' station batteries. Enclosure lll is the completed questionnaire for the RtzPatrick low pressure coolant injection (LPCI) system batteries.
. Enclosure IV is the completed questionna!re for the FitzPatrick instrument batteries.
The generic letter also PCked licensees to justify the existing design features, maintenance, surveillance and test procedures, and the basis for not including tne operational features cited. The design, maintenance, surveillance and test procedures for the DC power supplies at the Authority's Indian Point and FitzPatrick plants are reasona.ble alternatives to those cited by the staff. The design and operation of these systems were approved by thn NRC and are phrt of each plant's licensing basis. O 0 gP Tsseefu8$a kj i
.uva... a.
2-If you have any questions, please contact Mr. P. Kokolakis or Mr. J. A. Gray, Jr. Very truly yours,
'i C in
) k LF As_L -
) ~'\/ ,
s jn Rafph ElBeedle k Execbtivo Vico Presidant 1 Nuclear Generation STATE OF NEW YORK COUNTY OF WESTCHESTER ne Subscribed this c ) F dayend of (( Sworn y,, to boioroj/[pr1991
/- r -{ A4j f 7 / Notary Paulic
/ M J ANICE MANN Notary Public, Statt,of Now YorA C -
No. 4930701 Enclosures c.>md in westmester co,-- - Ccna ,%,oa Expires May 16,19 - ~ cc U.S. Nuclear Regulatory Commission Offico of the Resident inspector 475 Allendale Road U.S. Nuclear Rogulatory Commission King of Prussia, PA 19406 P.O. Box 136 - Lycoming, NY 13093 Resident inspector's Office Indian Point 3 Mr. Brian C. McCabo U.S. Nuclear Regulatory Commission Project Directorato 1-1 P.O. Box 337 Division of Roactor Projects l/II Buchanan, NY 10511 U.S. Nuclear Regulatory Commission Mai'. Stop 1482 Mr. Nicola F. Conicella, Project Manager Washington, DC 20555 Project Ditoctorate 11 Division of Reactor Projects-l/Il U.S. Nuclear Regulatory Commission Mail Stop 14B2 Washinginn, DC 20555
_- _ _ . ~ _ .__ . _. _ _ . _ _ _ _ , __ _ _ _ . __ IPN 91039 JPN.91000
, Enclosuro 1 Page 1 of 8 Questions (from Enclosurf * '.o Generic Letter 91-06) and Answ0rs Related to ladian Point t; Safety-Related DC Power Supplies in Generic Lottor 9106, the NRC staff requestod that licensoos provido the staff with information about their DC power supplios. Provided below is a restatomont of the questions contained in Enclosure 1 to Gonoric Lottor 9106, and the answers for the Indian Point 3 Nuclear Power Plant.
- 1. Unit: Indian Point 3 (IP3) 2.
- a. The number of indopondent redundant divisions of Class 1E or safety related de power for this plant is 3.
DC Busses 31, 32, and 33 are safety-related DC busses that supply safeguards and reactor protection systems. DC bus 34 is a safety-related bus that was added after the original plant design and also suppl;es DC power to the reactor protection system,
- b. The number of functional safety related divisions of de power nocessary to attain safo shutdown fo* this unit is 1 (2 following a Loss-of-Coolant Accident).
O. Does the control room at this unit have the following separato, independently annunciated a! arms and indications for each division of de powor? The Indian Point 3 control room (CCR) does not have separate and independent alarms and indications for each division of DC power, but has a single " Battery Charger Trouble" alarm. (See response to question 5 for add.tlonal information.)
- a. Alarms
- 1. Battery disconnect or circuit breakor open? No (See response to question 5 for additionalinformation.)
- 2. Battery chargor disconnect or circuit breaker open (both input ac and output de)?
No, but !! the battery charger is disconnected from its AC source, or if the charger output breaker or fuse opens: the Battery Charger Trouble-Alarm In the control room will be activated. Also, independent alarms are available at each charger.
IPN 91-039 JPN 91060
. Enclosuro 1 Pago 2 of 8
- 3. do system ground?
No, but a DC bus ground will activate the Battery Charger Trouble alarm, and a local alatm for the e"ected bus.
- 4. de bus undorvoltago?
No, but Oc bus undervoltage will activate the Battery Charger Trouble alarm, and a local alarm for the affected bus.
- 5. de bus osorvoltago?
No, but for battery chargers 31 and 32, an overvoltage condition will l activate the Battery Charger Trouble alarm and a local alarm for tho affected charger. (See response to question 5 for additional information.)
- 6. Battery charger failure?
No, but a battery chargc.- failure will activate the Battery Charger Trouble alarm and a local alae ' for the affected charger,
- 7. Battery dischargo?
No, but for batteries 31 and 32, battery discharge will activate the Battery Charger Trouble alarm and a local alarm for the affected battery. (See response to question 5 for additional Information.)
- b. Indications
- 1. Battery float charge current? No (See response to question 5 for additionalinformation.)
l
- 2. Battery circuit output current? No (See response to question 5 for additionalinformation.)
- 3. Battery discharge? No (See response to question -5 for additional information.)
- 4. Bus vo!tago?
No, but there is a bus selectable voltmeter in the control room. e
IPN 91039
+
JPN-91-060
. Enclosuro 1 Pago 3 of 8 i
- c. Does the unit havo writton procedures br responso to the abovo alarms and Indications?
IP3 has written procedures for response to the alarms and indications that are available. An " Alarm Responso Procedure" directs oporator action in response to the " Battery Charger Trouble Alarm." Station "Off Normal Operating Procedures" provide the operators with guidance for operating with DC system failurcs.
- 4. Docs this unit have indication of bypassed and inoperable status of circuit breakers or other devices that can be used to disconnect the battery and battery cho; gor from its de bus and the battery charger from its ac power source during mainton2.nco or testing?
If the battery charger is disconnected from its AC source, or if the charger output breaker or fuse opens, the Battery Charger Trouble Afarm in the contrcl room, and a local alarm, will be activated. Discorir.octing the battery from its bus will not cause an alarm. (Sea response to question 5 for additional inforrr.ation.) F
- 5. If the answer to any part of question 3 or 4 ls no, then provido information justifying the existing design features of the facility's safety rotated de systems.
Question 3- generalinformation The Indian Point 3 control room (CCR) Ms not have separato and indopondent alarms and indications for cach division of DC pvwor, but has a singlo " Battery Charger Troublo" alarm, and a bus sofoctablo voltmotor. Reflash capabliity is not provided for the category alarm window. The singlo category alarm, couplod with the local a! arms, providos assuranco of DC system availability because station oporating proceduros requiro watch personnel to identify the cause of a " Battery Charger Troublo" alarm. Thn proceduros also call for locally removing the input signal from the CCR " Battery Chcrger Troeble' alarm, to make the alarm window availablo for futuro alarms. The location of the chargers, directly below the CCR, minimizes the time during which subsequent battery charger alarms would be mcked. Also, the tours at four hour intervals by the nuc! car plant operators verify propor charger output lovels. This providos reliablo monitoring of battery charger status indopondent of the alarm circuit. Rosponding to DC system failuros !3 covered in the IP3 oporator training program. The IP3 design features are reasonable attornativos to those suggestod by the staff. Tho existing design featuros of the safety related DC system woro reviewod and approved by the NRC stati during the IP3 Operating Uconso review and are part of the licensing design basis. Question 3.a.1 - additional Information Disconnecting the battory from its bus will not cause an alarm. The breakers for tho battories (31,32, and 33) connected to safoguards systems can only bo opened manually. Administratively, a fino itom signoff is provided to assure that all battery breakers are closed following performance iosts (pts). For all battorios, the wockly l PT measures fut voltage directly at thn battery terminals if tho battery was l disconnected from the bus, the measured voltago would be below the required j l
l (PN-01-039 JPN 91-000 Enclosuro 1 Pago 4 of 8 values, Based on tho administrativo controls and the survoillanco tost, a battery disconnoct alarm is not considorod necessary. l l Question 3.a.5 - additional information Chargers 31 and 32 will shutdown on DC ovorvoltago and activato the Battory Charger Troubio alaim. Chargors 33 and 34 will not shutdown on DC bus overvoltage and activate the Battery Chargor Troublo alarm. However, the nuclear plant operators chock, log, and ovaluato all bus voltages during their tours (conducted at four hour intervals). Any out of specification reading, oither high or low, is identified, and appropriato corroctivo action is initiated by iho nuctoar plant nporator. Tho four hour chocks, plus the roliability demonstrated by the IP3 chargers, providos adoquato assuranco of DC bus availability. Question 3.a.7 - additional information For battorios 31 and 32, battery discharge will activato the Battery Charger Troublo alarm and a local alarm for tho effectod battary. Dischargo of battarios 33 or 34 l will not activato the Battery Charger Taable alarm. However, tho likely cause of I battery dischargo is failure of the chargor. Failure of any chargor will activato tho Battery Charger Troublo alarm. This, together with the monitoring of charger , otrput curront and voltage, providos assurance of proper charger operation, !
)
Question 3.b.1 - additional information l Battery float chargo current is not directly monitorod. Howevor, tho wookly PT battery voltage measuromont, together with nuctoar plant operator monitoring of charger output current and voltage ovory four hours, providos adoquato assuranco l of battery condition. ; Question 3.b.2 - additionai intarmation Battery circuit output current is not available in the CCR or locally During all normal operating conditions, each DC bus is supplied by the respectivo charger, Each battery has boon sized to carry its normal shutdown loads for two hours following a plant trip and loss of all AC power. Attor carrying shutdown loads for two hours, each charger can rochargo its battery within 15 hours, while also supplying its normal loads. Battery cu'put curront will be zero whenover the charger is in service. Failuro of the charger will cause an alarm. Thoroforo, a battery output current indicator is not considorod necessary. ! Question 3.b.3 - additional information i Battery dischargo indication is not directly availab'o in the CCR or locally. However, the alarms discussed in Question 3.a.7, together with tho four hour nuclear plant operator monitoring of charger output current and voltago providos assurance of battery condition, t_-______ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .
._. ~ __ __ -__
IPN 91039 JPN-910GO Enclosura 1 Page s of 8 i Ouestion 4 - additicaalinformation There is no indication of inoporablo or bypassed status for the breakers and fusos (for batterlos 31,32, and 33) that connect each battery to its bus. However, the breakers for the battorios (31,32, and 33) connected to cafoguards systems can
)
only be opened manually. Administratively, a line item signoff is provided to assure ! that tho breakers are clocod following performance tests (pts), in addition, if tho l battery is disconnected from the bus, it would be dotocted durirTi 3.7 wookly PT j (sco Question 3.a.1 additionalin'armation). ,
- 6. (1) Have you conducted a review of maintenanco and testing activitics to mlnimizo the l potential for human error causing more than one de drision to be unavailablo? No (See response to question 9 for additional Information.)
(2) Do plant proceduros prohibit maintenance or testing on rodundant dc divistorts at the same timo? Yes. A plant administrative proceduro requkos the Shift St;porvisor to verity that redundant equipment is available prior to romoving any safety related equipment from service.
- 7. Aro maintenance, surveillance and test procodures regarding station batteries conducted rout!ncly at this plant? Specifica!!y:
- a. At least enco por 7 days are the following verified to be 'vithin acceptab!c limits:
1, Pilot cell electrolyte lovel? Yes
- 2. Specific gravity or charging current? No (See response to question 9 for additionalinformation.)
- 3. Roat voltago?
Yes, total batt; - .' rininal voltage (on a float charge) is measured weekly.
- 4. Total bus voltage on float chas go? Yes
- 5. Physical condition of all ce!!s? Yes
- b. At least once por 92 days, or within 7 days after a battery discharge, overchargo, or
- if the pilot co!! readings are outside the 7 day surveillanco requirements are the following verified to be within acceptable limits;
, ... . .-. _. ~ .
- IPN 91-039
.. JPN-91000 Enclosuro 1 Page 6 of 8 4
W
- 1. Electrolyto lovel of each coll? -
The electrolyte level of each cellis checked at least once per 92 days.
- 2. The avorago specific gravity of all colts?
The average specific gravity of all cells is checked at least onco per 92 days.
- 3. The specific gravlty of each coll?
The specific gravity of each cell is checked at least once per 92 days. , 4. The average oloctrolyte temperature of a representativo number of cells? The average electro!yte temperature of a representative number of cells is checkul at least once per 92 days.
- 5. The float voltage of each coll?
The ficat voltage of each cell is checked at least once per 92 days.-
- 6. Visually -Inspect or measure resistanco of terminals - and connectors (including the connectors at the de bus)?-
Yes, all battery terminals, as well as the main and Intercell connectors, are visually inspected during the-weekly PT.- The connectors at the fuses and power panels are not included in the inspection.
- c. At least ovary 18 mnnths are the fo!!owing verified:
l' 1. Low resistanco of each connection (by tost)? . L l Yes, resistance of the battery intercell connectors is measured each L- refueling outage (currently every 18 months). L. 2 ' Physical condition of the battoty? Yes
- 3. Battery charger capability to deliver rated ampere output to the de bus?
L Testing of battery charpr maximum rated current is performed only
.when deemed approprian following charger maintenance. IP3 has a-spare battery charger that can be connected to any of the DC busses.
' To minimize DC bus voltage variations, the spare charger is normally used to recharge the batteries following the battery load test, while the
IPN-91-039
. JPN 9t Or4 Enclosuro 1 Pago 7 of 8 battery is still isolated from the bus. Due to the availability of the spare charger, a routine charger load test is considered ur.nocessary.
- 4. The capability of the battory to deliver its design duty cyclo to tho de bus? No (See response to question 9 for additionalInformation.)
- 5. Each individual co!! voltago is within acceptablo limits during the cervice tost?
Yes, the load test performed each refueling outage includet monitoring cell voltage to provent polarity reversal.
- d. At least overy 60 months, is capacity of each battery verified by performance of a dischargo test?
A battery load test is conducted each refueling outage (currently every 18 months). The test verifles battery capacity at the nominal 8-hour battery rating.
- e. At least annually, is the battery capacity verified by performanco dischargo test, if the battery shows signs of degradation or has reached 85% of the expected servico lifo? No (See response to question 9 for additionalInformation.)
- 8. Does this plant have operational features such that following loss of one safoty related do power supply or bus:
- a. Capability is maintained for ensuring continued and adequate reactor cooling? Yes
- b. Reactor coolant system integrity and isolation capabit!!y aro maintalnod? Yes
- c. Operating procedures, instrumentation (including indicators and annunciators),
and control functions are adoquate to initiato systems as required to maintain adequato coro cooling? Yes
- 9. If the answer to any part of question 6,7 or 8 is no, then provido your basis for not performing the maintenance, surycillance, and test procedures described and/or the bases for not including the operational features cited.
Question 6 (1) - additlonal information The Authority has not conducted a human factors review of DC system maintenance and testing activities, but administratively controts the availability of the DC systems. Maintenance and surveillanco test procedures applicable to the batteries, chargers and AC clectrical foods to the chargers requiro Shift Supervisor or Senior Reactor Operator signoff of the proceduro (PT) or wou clearance before work is initiated and after completion. Periodic test procedures include steps to
lPN 91039 JPN 91000 Enclosuro 1 Pago 8 of 8
~
assuro equipment oporability, Following correctivo maintenanco, a tost is - conducted to verify equipment oporability. Q uestion 7.a.2 additionalInformation Battery pilot cell spocific gravity is measured monthly. The one month interval is required by the IP3 Technical Specifications, and follows the gu! dance of IEEE-450-1987. Battcry charger output curront and voltago ato monitored ovory four hours. Tho present proceduros provido adoquato assuranco C battery condition. Question 7.c.4 additionalInformation Battery capacity is verified each refueling outago by a load test. The test is conducted at the nominal B-hour battory rating. Test acceptanco critorla is 80% battery capacity. The sofocted nominal tost dischargo rato does not envolope the IP3 DC bus load profilo. However, the load tost is considorod to adoquately verify battery capacity, Question 7.e - additional information I The battory capacity is verified each refueling outage by the battcry load tost. l Sinco the load test has boon conducted ondi refueling outago (18 month interval), the nood for a dual 5 year /1 yoar (at 85% life) test interval is not considorod necessary. The 20% battery capacity rosorve margin provides assurance of adequato battery capacity, IP3 battories 31/32 are prosently about 10 years old, aro at 90% capacity, and will be replaced during the Cyclo 8/9 Refueling Outago. I O
IPN 91039 JPN 910GO l Enclosuro 2 Page 1 of 4 Questions (from Enclosure 1 to Generic Letter 91-06) and Answers Related to James A. FitzPatrick Safety-Related DC Power Supplies (Station Batteries) I
'n Generic Lottor 91-06, tho NRC staff requestod that liconsoos provido the staff with information about their DC power supplies. Provided below is a restatomont of the questions contained in Generic Lottor 9106, Enclosure 1, and the answers for tho James A. FitzPatrick Nuclear Power Plant station battorios (71SB-1 and 71SB 2).
- 1. Unit: James A. FitzPatrick Nuclear Power Plant
- 2. ,
l a. The number of indopondent rodundant divisions of Class 1E or safety-related de l powor for this plant is two. (includo any separato Class 1E or safety rolated do, such as any de dedicated to the diosci gonorators.)
- b. The number of functional safety-related divisions of de power necessary to attain saf a snutdown for this unit is one.
- 3. Does the control room at this unit have the following separato, indopondently annunciated alarms and indications for each division of de power?
- a. Alarms
- 1. Battery disconnect or circuit breaker opon? No. Station battories are ,
directly connected to the de buses without any fuses, circuit breakers or disconnect switches.
- 2. Battory charpor disconnect or circuit breaker open (both input ac and output de)? Yos / Oss of ac power to the battery chargers will annunciate in the controi room.
- 3. de system ground? Yes
- 4. de bus undervoltagc? Yes.
- 5. de bus overvoltago? No. Bus voltage is displayed continuously in the FitzPatrick control room. Procedures require that bus voltage be checked and recorded at least once per shift.
- 6. Battery charger failure? No. Battery charger operation is monitored indirectly by the de bus undervoltage annunciabr, which alarms if bus '
voltage drops below battery EMF voltage. l I
IPN-91-039 l JPN 910GO Enclosuro 2 Pago 2 of 4
- 7. Battery discharge? No. Battery discharge is monitored Indirectly by a low de voltage annunciator which alarms In the control room when bus voltage falls below the battery EMF voltage,
- b. Indications
- 1. Battery float chargo current? Yes
- 2. Battery circuit output current? Yes
- 3. Battery dischargo? Yes. Battery float and discharge current are displayed on a single motor.
- 4. Bus voltago? Yes
- c. Dacs the unit have written procedures for response to tho abovo alarms and indications? Yes
- 4. Does this unit have !ndication of bypassed and inoporablo status of circuit breakers or other devices that can be used to disconnect the battery and battery charger from its dc bus and the battery charger from its ac power source during maintenance or usting? No.
Existing plant procedures require that the Shift Supervisor be notified before the battery system can be removed from service for maintenance or testing.
- 5. If the answer to any part of question 3 or 4 is no, then provido information justifying the existing design features of the facility's safety-related do systems. FitzPatrick's design features are reasonable altomatives to those suggested by the NRC as explained in the responses to the individual questions.
- 6. (1) Havo you conducted a review of maintenanco and testing activitics to minimize the potential for human error causing more than one de division to be unavailablo? Yes and (2) Do plant procedures prohibit maintenance or testing on redundant de divisions at the samo timo? Yes
- 7. Aro maintenanco, surveillance and test procedures regarding station batteries conducted routinely at this plant? Specifically:
- a. At least onco por 7 days are the following verified to be within acceptable limits:
- 1. Pilot cell electrolyto level? Yes
- 2. Specific gravity or charging current? Yes
- 3. Float voltago? Yes
- 4. Total bus voltage on float chargo? Yes
. IPN-91039 JPN 91-000 +
Enclosuro 2 Page 3 of 4 S. Physicalcondnion of all cells? Yes
- b. At least onco por 92 days, or within 7 days after a battery discharge, ovorchargo, or if the pilot cell readings are outside the 7-day surveillance requiremonts are tho ;
foliowing verified to be within acceptablo limits: '
- 1. Electrolyte levei of cach coll? Yes
- 2. The averego specific gravity of all cells? Yes
- 3. Tho specific grcvity of each coll? Yes 1
- 4. The average cloctrolyto temperaturo of a reprocontativo number of cells? Yos
- 5. The float voltage of each coll? Yes !
- 6. Visually inspect or moasuro resistanco of terminals and connectors (including the connectors at the de bus)? Yes
- c. At least ovory 18 months are the following verified:
- 1. Low resistanco of each connection (by lost)? Yes
- 2. Physical condition of the battery? Yes
- 3. Baticry charger capability to deliver rated ampero output to the de bus? Yes
- 4. The capability of the battory to delivnr its design duty cyclo to the de bus?
Yes
- 5. Each individual cell voltago is within acceptable limits dur... , ino servico
*ost? Yes
- d. At least every 60 months, is capacity of each battery veriflod by performance of a dischargo test? Yes
- o. At least annuaHy, is the battery capacity verified by performanco discharge tost, if the battery chows signs of degradation or has reached 85% of the expected servica lifo? Yes
' 8. ' Does this plant have opotational features such that following loss of ono safety related dc power supply or bus:
- a. Capabillty is mair;tained for ensuring continued and adog Jato reactor cooling? Yes
- b. Reactor coolant system intogrity and isolation capability are maintainod? Yos l
l
. IPN 91-039 JPNM-000 Enrlos.uro 2 Pago 4 of 4
- c. Operating proceduros, instrumentation (including indicators and annunciators),
and control functions are adoquato to initiato systems as required to maintain adequato coro cooling? Yes
- 9. If the answer to any part of question 6,7 or 8 is no, tho;t provido your basis for not performing the maintenanco, surveillanco, and test procedures described and/or lho bases for not including the oporational features cited. FitzPatrick's maintentance, surveillance and tosi procedures are reasonable alternatives to those suggested by the NRC as explained in the responses to the individual questions, i
? 1 l; o
IPN 91039 n JPN 91060 Enclosuro 3 l Page 1 of 4 Questions (from Enclosure 1 to Generic Letter 91-06) and Answers Related to James A. FitzPatr'ck l Low Pressure Coolant injection (LPCI) Battery l- Safety-Related DC Power Supplies In Gonoric l.ottor i1-06, the NRC staff requestori that licensees provido the staff with information about their DC po wer supplies. Provided below is a restatomont of the questions contalnod in Generic Lotter 9106, Enclosure 1, and the answers for the James A. FitzPatrick Nucioar Power Plant low presswo coolant injection (LPCI) batterles (71 BAT 3A and 71DAT-38) which are part of the 600 voit ac to 600 volt ac uninterruptable power supply Ior the LPCI motor-operated valvo electrical buses. I' l l
- 1. Unit: James A. FitzPatrick Nuclear Power Plant, !
2. 1
- a. The number of indopondent redundant divisions of Class 1E or safcty-related dc )
power for this plant is two. (includo any separato Class 1E or safety related de, l such as any de dodicated to the diosol generators.)
- b. The number of functional safoty related divisions of de power necessary to attain ;
safe shutdown for this unit is one. l
- 3. Does the control room at this unit have the following separato, Indopondently ,
annunciated alarms and Indications for each dMsion of de power?
- a. Alarms
- 1. Battery disconnect or circuit breaker cpon? Yes r
I' l 2. Battery charger disconnect or circuit breaker open (both input ac and output !- de)? Yes
- 3. de system ground? Yes L
- 4. dc bus undervoltage? Yes
- 5. dc bus overvoltago? No.
p 6. Battery charger failuro? Yes l- 7.- Battery dischargo? Yes l l I l
IPN 9t-039 JPN.910GO Enclosuro 3 Pago 2 of 4
- b. Indications
- 1. Battery float chargo current? No. Yhe charger normally suppilos the UPSs loverter with the battery in stand-by (i.e. on float charge.)
Indicatort are located on the UPS modules. Operational UPS status is monitored by annunciators in the control room which alarm on a loss of ac. TVo alarms are provided: UPS shutdown (major alarm) and trouble (miner alarm).
- 2. Battery circuit output curront? No. See response to question 3.b.1.
- 3. Battery discharge? No. See response to question 3.b.1,
- 4. Bus voltago? No. See response to question 3.b.1.
- c. Does the unit havo written procedures for responso to tho abovo alarms and indications? Yes
- 4. Does this unit havo indication of bypassed and inoperable status of circuit breakors or other devices that can be usod to disconnect tho battery and battery charger from its dc .
bus and the battery chargor from its ac power source during maintenanco or testing? Yes
- 5. If the answer to any part of questlon 3 or 4 is no, then provido information justifying the existing design features of the facility's safety related do syr. toms. FitzPatrick's design features are reasonable alternatives to those suggested by the NRC as explained in the responses to the individual questions.
- 6. (1) Have you conducted a review of maintenance and testing activitics to minimize the potential for human error causing more than one do division to be unavailablo? Yes and (2) Do plant proceduros prohibit maintenance or testing on rodundant de divisions at the same time? Yes
- 7. Aro maintenance, surveillance and tost proceduros regarding station batterlos conducted routinely at this plant? Specifically:
- a. At least onco por 7 days are the fol lowing verified to be within acceptablo limits:
- 1. Pilot co!! oloctrolyta lovel? Yes
- 2. Specific gravity or charging current? Yes
- 3. Float voltago? Yes
- 4. Total bus voltage on float chargo? Yes
- 5. Physical condition of all coils? Yes I
, IPN 91-039 JPN.91000 Enclosure 3 Pcgo 3 of 4
- b. At least onco por 92 days, or within 7 days after a battery dischargo, everchargo, or if the pliot cell readings are outsido the 7 day survoillanco requirements are the following ver!5od to be within acceptable limits:
- 1. Electrolyto levol of each coll? Yes
- 2. The average spocific gravity of all coils? Yes
- 3. The specific gravity of each coll? Yes
- 4. The average oloctrolyto temperature of a roptosentativo number of cells? Yes S. The float voltage of each co!!? Yes
- 6. Visually inspect or measuro osistance of terminals and connectors ,
(including the connectors at the dc bus)? Yet
- c. At least ovory 18 months are the following vori. lod:
- 1. Low resistance of each connection (by tost)? Yes
- 2. Physical condition of the battor>? Yos
- 3. Battory charger capability to dativer rated amporo output to the de bus? Yes A The capability of the battery to deliver its design duty cycis to tho de bus?
l Yes S. Each individual cell voltago is within acccptablo limits dt. ring the service tost? Yes
- d. At least every 60 months, is capacity of oach battory verified by performanco of a dischargo test? Yes e, At least annualty, is the battory capacity verified by performanco dischargo tost, if the battery shows signs of degradation or has reached 85% of the expected service lifo? Yes
- 8. Does inis plant havo operational features such that following loss of one safety-related dc L power supply or bus:
- A Capabl!ity ir. mainta!ned for onsuring continued and adoquato reactor cooling? Yes l
- b. Reactor coolant systom integrity and isolation capability are maintained? Yes l
l c. Operating proceduros, instrumentation (including indicators and annunciators), l and control functions are adequato to initiato systems as required to maintain l adequato coro cooling? Yes
. IPN 91-039 JPN 91-000 Enclosuro 3 Pago 4 of 4 9, If the answer to any part of question 6,7 or 8 is no, then provido your basis for not performing the rnalntonanco. survolUanco, and tost procedures described and/or the bases for not includirr the operational featuros cited. FitzPatrick's maintenance, survel!!ance and tes ocedures are reasonable alternatives to those suggested by the NRC as explaine i tne responses to the individual questions.
o t
am- un 4. 4 +=h- M-' . A s~ 44 -.-- IPN 91039 I' JPN.91000 Enclosuro 4 Pago 1 of 4 1 Questions (from Enclosure 1 to Generic Letter 9106) and Answers Related to James A. FitzPatrick Instrument Batterles 1 in Gonoric 1.ottor 9106, the NRC staff roquestod that licensoos provido the staff with intorination a'oout their DC power supplios. Providod below is a restatomont of tho questions conttJnod in Generic Lettor 9106, Enclosuro 1, and tho answers for the James A, FitzPatrick Nuc' oar Power ! Plant Instrument batterlos (7118-1,711B 2,711B 3 and 7118-4). The loads on the electrical bussos supplied by thoso battorios includo SRMs (sourco rango 1 monitors), IRMs (intormodiato rango monitors), and post accident roactor building radiation l raonitors. . Applying the definition of class 1E in the 1980 odition of IEEE 308, those instrument battorios are not class 1E because they are not *ossential to omorgency reactor shutdown, containment isolation, reactor coro cooting, and containment and rcactor heat romnval...' Tho Authority has completed a questionnalto for those instrumont battories to supply tho NRC staff with completo and accurato information about the RtzPatrick de power supplics.
- 1. Unit: James A. FitzPatrick Nuclear Power Plant, 2.
- a. The number of Indopondent rodundant divisions of Class 1E or safoty-rotated de power for this plant is two (loclude any coparato Class 1E or safoty related de, such as any de dodicated to the diosol gonorators.)
- b. The number of functional sdoty related divisions of do power nocessary to attain safo shutdown for this unit is zero.
- 3. Does the control room at this unit have the following separato, Indopondently annunciated alarms and indications for each division of de powor?
- a. Alarms
- 1. Battory disconnect or circuit breakor opon? No
- 2. Battery charger disconnect or circuit breaker opon (both input ac and output - (h de)? No
- 3. dc systom ground? No
- 4. de bus undervoltage? Yes
- 5. de bus overvoltago? Yes
IPN-01-039 i l JPN 91-OS3 Enclosuro 4 Pago 2 of 4 -
- 6. Battoly chargor failuro? No
- 7. Battory dischargo? No l b. Indications
- 1. Battery float chargo curront? No
- 2. Battcry circuit output current? No
- 3. Battcry discharge? No
- 4. Bus voltago? No
! c. Does the unit have writton proccduros for rotponso to the above alarms and
- . Indicatforis? Yes l
- 4. Does this unit have indication of bypassed and inoperable status of circuit breakers or other devicos that can bo used to disconnect the battery and battery charger from its dc bus and the battery charger from its ac power source during maintenance or testing? No l
S. If the mswer to any part of question 3 or 4 is no, then provide information justifying the cdsting design featutes of the facility's safoty related de systems. Applying the definition of Clast 1E of IEEE-3081980, these instrument batteries are not class 1E l because they are not " essential to emergency reactor shutdown, containment l laolation, reactor core cooling, and containment and reactor heat removal..." The i loads on the electrical bussos supplied by these batteries include SRMs (source l range monitors), IRMs (Intermediate range monitors), and post-accident reactor l l building radiation monitors. FitzPatrick's design featuros are reasonable , alternatives to those suggested by the NRC considering the primary function of these instruments.
- 6. (1) Have you conducted a review of maintenanco and testing activitlos to minimizo the potontial for human orror causing more than one de d; vision to be unavailablo? Yes and (2) Do plant proceduros prohibit maintenance or tost!ng on rodundant de divisions at tho l same timo? Yes
- 7. Are maintonar.ce, survoillanco and test proceduros regarding station battories conducted routinely at this plant? Specifically:
- a. At least once por 7 days are the following verified to be within acceptable limits:
- 1. Pilot cell electrolyte lovel? Yes
- 2. Specif_c gravity or charging current? Yes
- 3. Float voltago? Yes
. IPN 91-039 JPN 91-000 Enclosure 4 Pago 3 of 4
- 4. Total bus voltaga on float chargo? Yen
- 5. Physical condition of a!! cells? Yes
- b. At least onco por 92 days, or with!n 7 dayt. after a battery dischargo, overcharge, or if the pilot cell readings are outside the 7 day survoillanco requirements aro tho following verified to be witlin acceptablo limits:
- 1. Electrolyte lovel of each coll? Yes
- 2. The averago specific gravity of aJl celts? No. The Authority is revising the quarterly test procedure to assure that the average specific gravity of all cells is within acceptable limits. The now procedure veill be implemented nolaterthan April 1,1992.
- 3. The specific gravity of each coll? Yes
- 4. The averago cioctrolyte temperaturo of a representativo number of cells? Yes
- 6. The float voltage of each ce!!? Yes
- 6. Visually inspect or measure resistance of terminals and connectors (including ino connectors at the de bus)? No
- c. At least overy 18 months are the following verifioc:
- 1. Low resistanco of each connection (by test)? No
- 2. Physical condition of the battery? No
- 3. Battery charger capability to deliver rated ampere output to the de bus? No
- 4. The capability of the battery to deliver its design duty cyclo to tho dc bus? No
- 5. Each individual coil voltago is within acceptable limits during the service test? No
- d. At least every 60 months,is capacity of each battery verified by performanco of a dischargo test? No
- e. At least annually, is the battery capacity verified by pctformance dischargo test, if the battery shows signs of degradation or has reached 85% of the expected servico life? No
- 8. Does this plant havo operational features such that following loss of one safety related do power supply or bus:
IPN 91039 JPN-91-000
- a. Enclosuro 4 Pago 4 of ?.
b, Capability is maintainod for ensuring continuod Reactor coolant system intogrity andand adequato isolati roactor cooling? Yes c. Oporating proceduros, instrumentation (includion capabil and control adoquate functions coro cooling? Yes are adoquato to initiato systemng in 9, s as required to maintain if ino answer to snv part of question 6 7 bases fnt not including the operational toatperformin the NRC. See the n. ures cited.toFitzPatrick's response questio 5survolitanceinalntonance e attornativos to thoso suggca,ted by \
--- ---'}}