ML20198A516
| ML20198A516 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 12/19/1997 |
| From: | Kelly G NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| TAC-M97197, NUDOCS 9801060004 | |
| Download: ML20198A516 (20) | |
Text
_
l l December 19,1997 l
LICrNSEE: IES Utilities Inc.
FACILITY: Duane Arnold Energy Center
SUBJECT:
SUMMARY
OF DECEMBER 17-18,1997, MEETING ON RESPONSES TO REQUESTS FOR ADDITIONAL INFORMATION (RAls) ON THE DUANE ARNOLD ENERGY CENTER (DAEC) IMPROVED TECHNICAL SPECIFICATIONS (TAC NO. M97197)
On December 17 and 18,1997, a public meeting was held between the NRC staff and IES Utilities Inc. (licensee) that addressed responses provided by the licensee regarding RAls on the DAEO' Improved Technical Specifications (ITS). The staff and licenae discussed responses to RAls on DAEC ITS Sections: 3.6 and 3.8. The discussions resulted in or documented closure of most of the RAls. Enclosura 1 is a list of attendees. Enclosure 2 is a copy of handvuts from the meeting.
Original signed by:
opgtro/y f dr Glenn B. Kelly, Senior Project Manager Project Directorate lil 3 Division of Reactor Projects ill/IV Office of Nuclear Reactor Regulation Docket No. 50-331
Enclosures:
As stated cc'wlencts: See next page 0
Distribution w/enclolutes 1 and 2:
Docket' PUBLIC PDill 3 R/F GGrant, Rlli GKelly Distribution w/ enclosure 1 (email): 1 ACRS OGC RGiardina (
SCollins EAdensam (EGA1) ETomlinson )
FMiraglia 1Tjader WBeckner TMartin DOCUMENT NAME: G:/DUANEARN/97197MTU.WPD OFFICE PM PDild, ,) E LAPDill-3 ]E , , ,, c , , .
NAME GKelly //) M nn)_QnC DATE 12/19TI i 121 47 '
OFFICIAL RECORD COPY
~
9901060004 97121f l PDR ADOCK 05000331 p PLR
- - _ _ - - _ _ _ _ _ _ - _ _ ____ ~
y December 19,1997 LICENSEE: lES Utilities Inc.
FACILITY: Duane Arnold Encay Center
SUBJECT:
SUMMARY
OF DECEMBER 17-18,1997, MEETING ON RESPONSES TO REQUESTS FOR ADDITIONAL INFORMATION (RAls) ON THE DUANE ARNOLD ENERGY CENTER (DAEC) IMPROVED TECHNICAL SPECIFICATIONS (TAC NO M97197)
On December 17 and 18,1997, a public meeting was held between the NRC staff and IES Utilities Inc. (licensee) that addressed responses provided by the licensee regarding RAls on the DAEC Improved Technical Specifications (ITS). The staff and licensee discussed .y responses to RAls on DAEC ITS Sec* ions: 3.6 and 3.S. The discussions resulted in or documented closure of most of the RAls. Enclosure 1 is a list of attendees. Enclosure 2 is a copy of handouts from the meeting.
Original signed by:
Glenn B. Kelly, Senior Project Manager Project Directorate lll 3 Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation Docket No. 50-331
Enclosures:
As stated cc w/encls: See next page D,stributlen w/ enclosures 1 and 2:
Docket PUBLIC PDill 3 R/F GGrant, Rill GKelly Distribution w/enelor.ure 1 (email):
ACRS OGC RGiardina SCollins EAc:ensam (EGA1) ETomlinson FMiraglia TTjader WBeckner TMartin DOCUMENT NAME: G:/DUANEARN/97197MTU.WPD lOFFIC8i PM PDitL ,} E LA.PDill-3 3E NAME GKelty //))K eAm 9nC DATE 12/19/5f7 1 12//67 '
OFFICIAL RECORD COPY
, ** *800g y 1 UNITED STATES NUCLEAR REGULATORY COMM!SSION WASHINGTON, D.C. 300eH001 .
l
\*...e December 19,1997 LICENSEE: IES Utilities Inc.
FACILITY: Duane Amold Energy Center
SUBJECT:
SUMMARY
OF DECEMBER 17 -18,1997, MEETING ON RESPONSES TO REQUESTS FCR ADDITIONAL INFORMATION (RAls) ON THE DUANE ARNOLD ENERGY CENTER (DAEC) IMPROVED TECHNICAL SPECIFICATIONS (TA0 NO. M97197)
On December 17 and 18,1997, a public meeting was held between the NRO staff and IES Utilities Inc. (licensee) that addressed responses provided by the licensee regarding RAls on the DAEC Improved Technical Specifications (ITS). The staff and licensee discussed responses to RAls on DAEC ITS Sections: 3.6 and 3.8. The discussions resulted in or documented closure of most of the RAls. Enclosure 1 is a list of attendees. Enclosure 2 is a copy of handouts from the meeting.
l i
- 'W I Glenn B. Kell , Senior roject anager Project Directorate 1113 l Division of Reactor Projects lil/IV Office of Nuclear Reactor Regulation Docket No. 50-331
Enclosures:
As stated cc w/encis: See next page l
l l
1 Duane Arnold Energy Center IES Utilities Inc.
CCI Jack Newman, Esauire Kathleen H. Shea, Esquire ,
Morgan, Lewis, & Bockius 1800 M Street, NW.
Washington, DC 20036-5869 Chairman, Linn County '
Board of Supervisors Cedar Rapids, IA 52406 IES Utilities Inc.
ATTN: Gary Van Middlesworth Plant Superintendent, Nuclear-3277 DAEC Road Palo, IA 52324 John F. Franz, Jr. '
Vice President, Nuclear Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324 ,
Xen Peveler Manager, Nuclear Licensing Duann Arnold Energy Center 3277 DAEC Road Palo. IA 52324 e U.S. Nuclear Regulatory Commission Resident Inspector's Office Rural Route #1 Palo, IA 52324 Regional Administrator U.S.-NRC, Region III 801 Warrenville Road Lisle, IL 60532-4531 Parween Baig Utilities Division Iowa Department of Commerce Lucas Office 8t:11 ding, 5th Floor Des Moines, IA 50319 ,
Lee Liu Chairman of the Board and Chief Executive Officer IES Utilities Inc.
l- 200 First Street, SE.
P.O. Box 351 Cedar Rapids,-IA 52406-0351
ATTENDEES OF DECEMSFR 17.1997 MEETING ON DAEC ITS RAI RESPONSES Name organization Glenn Kelly NRC Ed Tomlinson NRC Tommy Le NRC Carl Schulten NRC Roy Tony' Browning IES Joel Easton IEG Ken Putnam lES Ken Peveler IES Jeff Mahannah IES Timothy Allen IES ATTENDEES OF DECEMBER 1,8.1997. MEETINfa ON DAEC ITS RAI RESPONSES blamt Oraanization Glenn Kelly NRC Robert Giardina NRC T. Bob Tjader NRC Roy Tony' Browning IES Joel Easton IES Ken Putnam lES Ken Peveler IES Jeff Mahannah IES Timothy Allen IES Eric Sorenson IES ENCLOSURE 1 i
i t
I HANDOUTS FROM MEETING WITH f IES UTILITIES INC. ON DUANE ARNOLD r ENERGY CENTER IMPROVED TS RAIS ,
12/17/97 to 12/18/97 F
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ENCLOSURE 2 i
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1 Typkal process for taking a battery cell eat of service.
- 1. Calculate mmimum cell voltage requirement (Mimmum banery voltage is 105 VDC for the 58 cell 125 VDC 1,anery and 210 VDC for the 116 cell 250 VDC banery):
125 VDC with 0 cells 005: 105/58-1.81 ne 125 VDC mith I cell OOS: 105/57=1.84 vpc 250 VDC with 0 cells OOS: 210/116-l.81 vpc l 250 VDC with I cell OOS: 210/115-1.8) vpc i
- 2. Review cell voltages recorded at end last Service Discharge Test. Venfy that cell voltages for all inservice cells is greater than the muumum required for 1 cell OOS. (i.e.1.84 vpc for 125 VDC, 1.8) vpc for 250 VDC)
- 3. Rear : 'e cell from service. To prevent overcharging and maintain same individual cell float voltage, reduce overall float voltage to to account for cell OOS. (Note: for opumal performance with all cells iraervice, float voltage is normally maintained at 2.25 vpc or 130.5 VDC for toe 125 VDC banery and 261 VDC for the 250 VDC battery) Adjust float voltage to; 125 VDC with I cell OOS: 2.25x57-128 VDC 250 VDC with I cell OOS: 2.25x115-258 VDC Note: Battery ID93 uses the same type of be.ttery cells as the station batteries and are procurred and maintained as QLI. ID93 powers the plant telephone system and CARDOX. These systems are non safety related. Therefore, cells from ID93 are continuously available as spares.
References:
ESMP BATTRY-C173-01
. ESMP BATTRY.L270-01 Convesation with J.McOough 17115/97
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- 24 Volt DC Battery Supported Loads IDiQ lagd Response to Loss of Power Associated ITS Spec.
ERM's A and C Fail Low Tripped 3.3.1.2 1RM's A, C, and E Fail Low Tripped 3.3.1.1 Refuel Floor Exhaust RM 'A' Fails Low Tripped 3.3.6.1 function 2.e and 3.3.6.2 Function 4 Off Gas RM 4116 'A' Fails Low Tripped 3.3.6.1 Function 2.c Misc 'A' side Process Fail Low None Radiation Monitors 1D60 SRM's B and D Fail Low Tripped 3.3.1.2 IRM's B, D, and F Fail Low Tripped 3.3.1.1 Refu-l Floor Exhaust RM 'B' Fails Low Tripped 3.3.6.1 Function 2.c and 3.3.6.2 Fanction 4 Off Gas RM 4116 'B' Fails Low Tripped 3.3.6.1 Function 2.c Misc. 'B' side Process Fail Low None Radiation Monitors Summary of response to loss of 24 VDC In response to a loss of one division of 24 volt DC, a rod withdrawal block and a half-scram will occur if the Mode Switch is not in run. The associated division of Group '3' Primary Containment Isolation will occur and the Secondary Containment will isolate.
The Standby Gas Treatment System associated with the division will start.
Miscellaneous non-safety related radiation monitors will fait downscale. The operator will enter the Conditions associated with inoperability of the instrumentation listed
., above. In each case the Required Action for inoperability of the associated channels of instrumentation is to place the ast,ociated channel in the tripped condition. In each case m.-._
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1 l
this is also the fall safe response of the equipment to a loss of power. There are no
- complex interactions between the design or safety functions of the associated j instrumentation, nor does the inoperability of the supponed instrumentation create complex Technical Specification actions. The primary pumose fro having a suppon !
system LCO within the TS is to simplify the actions and potentially provide some j relaxation / delay in taking the actions ofinoperable supponed systems LCOs. in panicular !
when there are multiple diverse systems supproted by the same suppon system (ref LCO ;
j 3.0.6). This is not the case with 24 VDC. The LCO 3.0.6 relaxation is not needed and is not supponed by the DAEC 's CLB as the CTS requires an irnmediated cascade to the - !
supported intruments LCO Actions. De 24 VDC batteries do not in themselves satisfy ;
any of the screening criteria of 10CFR 50.36 for inclusion in the Technical (
Specifications. He specifications for the supported instrumentation are fully adequate to ;
ensure the required functions are available. Re required actions of the CTS associated :
, with inoperability of the 24 VDC batteries is simply to declare the supported .
l instrumentation inoperable. This is fully implemented in the ITS via LCO 3.U.2 and the j definition of Operable Operability. Relocation of requirements of the CTS associated with 24 VDC Batteries to the Technical Requirements Manual is appropriate.
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h ib 0 91 W 3 October 23,1997 I
Page 2 of 5 s A f y1 l
- 1. Summary of NUREG 1433 Surveillance 9equirements Related to CRF # 9556 A. Lots of Offsite Power (LOOP) Condition Only
- 1. SR 3.8.1.11: Verify on an actual or simulated loss of offsite power signal:
- a. De-energization of essential buses; !
- b. Load shedding from essential buses: ,
- c. DG auto start from standby condition and:
- l. onergizes permanently connected loads in s 10 seconds, ,
ii. onergizes auto-connected emergency loads in the proper timed sequence.
iii. achieves rated voltage iv. schieves rated frequency, and
- v. supplies permanently connected and auto connected emergency loads for 2 5 minutes.
- 2. DAEC Response to a LOOP Condition Only Related to CRF # C556 The Loss of Offsite Power (LOOP) condition is sensed as either: 1) essential bus degraded voltage, or 2) an undervoltage condition on the secondary windings of both the Startup and Standby transformers. The electrical plant response to each of these '
conditions is as follows:
- a. Degraded Voltage
- 1. Trips Standby transformer supply breaker to essentiM bus, ii. Blocks closure of Standby transformer supply breaker to essential bus.
iii. Trips Startup transformer supply breaker to essential bus.
iv. Blocks closure of Startup transformer supply breaker to essential bus. ;
- v. Energizes relay 195 3 (195 4). Relay 195-3 (195 4) when energized provides contact closure in DG start circuit A, DG 6 tart circuit B, and LOOP Loss of Coolant Accident (LOCA) load shedding logic.
- b. Undervoltage condition on the secondary v.dndings of both the Startup and Standby transformors i
- 1. Trips Standby transformer supply breaker to essential bus,
- 11. Blocks closure of Standby transformer supply breaker to essential bus.
iii. Trips Startup transformer supply breaker to essential bus.
iv. Blocks closure of Startup transformer supply breaker to essential bus.
- v. Energizes relay 195-3 (195-4). Relay 195 3 (195-4) when enc,gized provides contact closure in DG start circuit A DG start circuit B, and LOOP-Loss of Coolant Accident (LOCA) load shedding logic,
- c. As a result of degraded voltage or undervoltage condition on the secondary windings
' of both the Startup and Standby transformers, the essential bus is isolated from i offsite power, This results in a bus undervoltage condition (loss of voltage) which results in the following:
October 25,1997 Pcge 3 of 5 l ii. Closure permissive for DG to essential bus supp!y breaker. ;
I
- d. The DGs resupply the essential buses. No load sequencing is utilized to protect the DGs for the case of a LOOP condition only, ,
B. Loss nf Coolant Accident (LOCA) Condition Only f
_ 1. OR 3.8.1.12: Verify on an actual or simulated ECCS initiation signal each DG auto-starts from standby condition end:: l
- a. In s 10 seconds after auto start and during tests achieves rated voltage;
- b. In s 10 seconds after auto start and during tests achieves rated frequency; ,
- c. Operates for 2 5 minutes.
- d. Permanently connected loads remain energized from the offsite power system; and
- e. Emergency loads are energized from the offsite power system in the proper timed sequence.
< a. Relay E21 A K11 A (E21 A K11B) is energized on either of two conditions: 1) Drywell Pressure - High or 2) Reactor Vessel Water Level - Low Low Low. Relay E21 A K11 A (E21 A K118) when energized provides contact cicsure in DG start circuit A, DG start circuit B, and load shedding logic relay 196 3 (1964),
- b. Relay 196 3 (196 4) when energized provides contact closure in the LOOP LOCA load shedding logic and River Water Supply Emergency Makeup logic.
- c. The CS (5 seconds) and RHR pumps (10 and 15 seconds) are sequenced onto the essential buses whenever they are started in response to a LOCA condition.
C. LOOP-LOCA Condition I
- 1. SR 3.8.1.13: Verify on an actual or simulated loss of offsite power signal in conjunction with an actual or simulated ECCS initiation signal:
- a. De energization of essential buses; ,
- b. Lead shedding from essential buses;
- c. DG auto-start from standby condition and:
- 1. onergizes permanently connected loads in s 10 socorWs,
- 2. energizes auto-connected emergency loads in the proper timed sequence.
- 3. achieves rated voltage
- 4. achieves rated frequere/, and
- 5. supplies permanently connected and auto connected emergency loads for 2 5 minutes.
- 2. DAEC Response to the LOOP. LOCA Condition Related to CRF # 9556 The only change in response when compared to the LOOP only and LOCA only cases is that addhional LOOP-LOCA load shedding of MCCs 1B33,1835,1943,1945; and the r CRD, GSW, and RHRSW pumps.
I i
- - - October 23,1997 Page 4 of 5 t
', i
- 11. Summary of ITS Surveillance Requirements Related to CRF # 9556 [
A. SR 3.8.1.13: Verify on an actual or simulated loss of offsite power signal in conjunction with l an actual or simulated ECCS initiation signal: ;
- 1. De-energitation of essential buses; l
- 2. Load shedding from essential buses; !
3- DG auto start from standby condition and:
- a. onergizes permanently connected loads in s 10 seconds,
- b. onergizes auto-connected emergency loads in the proper timed sequence. i f
- c. achieves rated voltage ;
- d. achieves rated frequency, ent) e supplies permanently connected and auto-connected emergency loads for 2 5 :
minutes. 1 L
, B. The DAEC Response to the LOOP. LOCA condition is as described above. It is a combination
! of the LOOP only response and LOCA only response with the addition of LOOP LOCA toed shedding.
i 111. Difference Between NUREG SR and ITS SR Requirernents ,
, A. DG Response .
l As described in the ITS BASES for SR 3.8.1.13. "in lieu of multiple demonstrations of DG ,
starting and achieving rated voltage and frequency in the specifed time from each of 'he various start signals (LOOP, LOCA and LOOP /LOCA), and operation for 2 5 minutes, testing l
that adequately shows the capability of the DG to start from sech of the sigr,als is acceptable. l I
As shown in the attached DG logic diagrams (M015-006 <1>, M015-006 <1 A>) 1G31 (1G21) f receives LOOP only [ relay 195 3 (195 4)) and LOCA only [ relay E21 A K11 A (E21 A-K118)]
start signals in parallelin both DG start circuits A and B.
Current testing in STP 48A002 CY confirms DG relays ESA and ESB are energized in t response to a simulated LOOP only condition without allowing the DG to start. Then, with the l LOOP relay 195 3 (1954) contacts into the DG start circuit A and B logics are blocked open, l- a LOOP-LOCA condition is simulated. DG start on a LOCA signal is vertfled by recorder :
I - traces to be within the required time. DG relays ESA and ESB se confirmed to be energized,
I
- Since the DG response is the same for alther a LOOP only or LOCA only condition, verification of ESA and ESB energized for each signal edequately shows the capability of the DG to start from each of the signals without multiple DG starts.
l B. LOOP Response Channel funeonal test, channel calibration, and logic system functional test requirements for:
Undervoltage (Dograded Voltage), and 3) 4.16 kV Emergency Transformer Supply Unde: voltage functions are provided in ITS Section 3.3.8.1. These requirements are sufficent to ensure operability of these functions without requeng verification of response to an actual ,
- or simulated loss of offsite power signal, ,
l:
L .
i
- '
- October 23,1997 '
l Page 5 of 5 Current testing in STP 48A002-CY confirms that a simulated LOOP only condition does not produce a LOOP LOCA load shed.
B. - LOCA Response ,
Channel functional test, channel calibration, and logic syttom functional test requirements for both the Drywell Pressure . High and Reactor Vessel Water Level Low Low Low functions are provided in ITS Section 3.3.5.1. ;
Current tasting in STP 48A002 CY confirms that a simulated LOOP LOCA condition resuns in proper operation of the Rivar Water Supply Emergency Makeup logic and load sequencing of the CS (5 seconos) and RHR pumps (10 and 15 seconds) onto the essential buses. Since these responses are the same for either a LOCA only condition or a LOOP LOCA condition, there is no need to do separate testing for the two conditions.
Current testing in STP 48A002 CY dona DQ1 confirm that a simulated LOCA only condition does not produce a LOOP LOCA load shed. The current testing can be easily modified to venfy that LOOP LOCA load sheddhg does not resuit from a LOCA only signal.
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