ML092730275

Summary of Meeting with Union Electric Company to Discuss Proposed Risk-Informed Technical Specification License Amendment for Callaway Plant, Unit 1, and Future Adoption of Initiative 4b

ML092730275
Person / Time
Site:	Callaway
Issue date:	10/15/2009
From:	Thadani M Plant Licensing Branch IV
To:
Thadani, M C, NRR/DORL/LP4, 415-1476
References
Download: ML092730275 (23)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 15, 2009 LICENSEE:

Union Electric Company FACILITY:

Callaway Plant, Unit 1

SUMMARY

OF SEPTEMBER 17, 2009, MEETING WITH REPRESENTATIVES OF UNION ELECTRIC COMPANY, LICENSEE FOR CALLAWAY PLANT, UNIT 1 ON PROPOSED RISK-INFORMED LICENSE AMENDMENT On September 17, 2009, a Category 1 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Union Electric Company, the licensee for Callaway Plant, Unit 1, at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, Maryland. The purpose of the meeting was to discuss the licensee's plan and approach to submit a risk-informed license amendment request (LAR) to extend the completion time for certain balance of plant (BOP) engineered safety feature actuation system (ESFAS) actuation signals. A list of attendees is provided as Enclosure 1.

In its presentation, the licensee stated that the BOP ESFAS provides signals to initiate ESFAS to control and mitigate consequences of fault conditions in actuation signals for containment purge isolation, fuel building ventilation isolation, auxiliary/feedwater actuation, low suction pressure, and steam generator blowdown sample isolation. The licensee plans to request the LAR to address its inability to perform repairs in the allowed outage times. The licensee stated that on February 19, 2009, its power supply SA036D PS-1 failed and resulted in a plant shut down to Mode 3 due to its inability to replace the failed power supply in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of allowed outage time. To avoid future such shutdowns or requests for enforcement discretions, the licensee plans to request an extension of completion time from 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, using the risk-informed rationale for acceptability of the change. The licensee's presentation viewgraphs are provided in Enclosure 2.

The licensee's presentation included its plans for submitting the risk-informed LAR. The licensee plans to upgrade its probabilistic risk assessment (PRA) capability to Regulatory Guide (RG) 1.200, "An Approach for Deterring the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities," guidance, and submit LARs for risk-informed initiative 4b, "Risk Managed Technical Specifications," and risk-informed initiative 5b, "Surveillance Frequency Control Program."

The licensee stated that the approval of LARs would obviate the need to ask NRC for discretions of regulatory enforcements, or shutting down the plant when recovery actions cannot be completed in the allowed outage times (completion times).

The NRC staff expressed appreciation for the licensee's presentation, and offered insights on expectations for PRA upgrade to RG 1.200 guidance, and on licensee's plans to submit LARs for risk-informed initiatives 4b and 5b. The NRC staff discussed its experience with the approval of pilot amendments for both initiatives.

- 2 There were no public participants present, and no Public Meeting Feedback forms were submitted at the meeting.

If there are any questions or comments, please direct inquiries to me by telephone at 301-415-1476 or by electronic mail to Mohan.Thadani@nrc.gov.

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Mohan C. Thadani, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-483

Enclosures:

1. List of Attendees

2. Licensee presentation cc w/encl: Distribution via Listserv

LIST OF ATTENDEES U.S. NUCLEAR REGULATORY COMMISSION CATEGORY 1 MEETING ON SEPTEMBER 17, 2009, WITH REPRESENTATIVES OF UNION ELECTRIC COMPANY Name Affiliation Telephone Union Electric Company Michael Hudson Ameren UE 573-676-8863 Scott Sandbathe Ameren UE 573-676-8528 Scott Maglio Ameren UE 573-676-8719 Bert Yates Ameren UE 314-225-1702 Mark Walz Scientech 618-281-4881 Hogbing Jians Ameren UE 314-974-8609 U.S. Nuclear Regulatory Commission Barry Marcus NRRJDE/EICB 301-415-2823 Greg Casto NRRJDSS/SBPB 301-415-4072 Cliff Doutt NRRJDLRJRER2 301-415-2847 Donnie Harrison NRRJDRAIAPLA 301-415-2470 Mohan Thadani NRRJDORLlLPL4 301-415-1476

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AGENDA Meeting between NRC and Union Electric Company (AmerenUE)

Thursday, September 17, 2009 8:30 AM - 10:30 AM

• Introductions

• Callaway's Integrated Plan to Transition to Risk-Managed Technical Specifications (TSs)

• Balance-of-Plant Engineered Safety Features Actuation System (BOP ESFAS) Design and Power Supply Issues

• License Amendment Request - Draft TSs and Bases Changes

• Probabilistic Risk Assessment

• Questions and Answers

• Comments from Public

• Adjourn

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CALLAWAY PLANT RISK-INFORMED AMENDMENT REQUEST 24-HOUR BOP ESFAS COMPLETION TIME Regulatory Affairs Strategic Planning 2009 2010 2011 2012 LAR BOP ESFASAOTI

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4th Qtr 2011 TSTF-505 RG 1.200 Approval LAR PRAModel RG 1.200

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Peer -..-/' 41h Qtr Review 2010 I.

By 11120/09 PRA Upgrade I I

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to RG 1.200 October March I

2010 2011 Draft Implementing PRA Gap Procedures. QS Training NRC Analysis Modules. per NEl 04-10 Approval Implement RMTS 5b I Draft LAR (Surveillances)

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RMTS 4b I (Completion Times) lSI Qtr 2011

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CALLAWAY PLANT RISK-INFORMED AMENDMENT REQUEST 24-HOUR BOP ESFAS COMPLETION TIME BOP ESFAS

• BOP ESFAS provides signals to initiate actuation of the Engineering Safety Features systems in order to control and mitigate the consequences of such faults as Condition II, III and IV events defined in ANSI N18.2-1973.

• Actuation Signals Containment Purge Isolation Signal (CPIS)

Fuel Building Ventilation Isolation Signal (FBVIS)

Control Room Ventilation Isolation Signal (CRVIS)

Auxiliary Feedwater Actuation Signal (AFAS)

Low Suction Pressure (LSP)

Steam Generator Blowdown Sample Isolation Signal (SGBSIS)

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CALLAWAY PLANT RISK-INFORMED AMENDMENT REQUEST 24-HOUR BOP ESFAS COMPLETION TIME BOP ESFAS Power Supply Failure

• SA036D PS-1 power supply failed at 0228 on 2/19/09, resulting in a plant shutdown to Mode 3 due to the inability to replace it within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

The shutdown was completed at 0817. The BOP ESFAS system was restored at 1009.

• The two Sorensen model power supplies (PS-1 and PS-2) are both obsolete.

• Both models are being reverse engineered for comprehensive replacement during Refuel 17.

• The requested amendment would obviate the need for any future request for enforcement discretion (NOED) due to BOP ESFAS failure.

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8N26-1 PS-3 PS-1

-15 PS-2 48VDC ~ I15VDC I 8N28-1

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CALLAWAY PLANT RISK-INFORMED AMENDMENT REQUEST 24-HOUR BOP ESFAS COMPLETION TIME BOP ESFAS Power Supplies SA036A SA036D Channel I Logic I NK5110 I 8N26-1 125 VDe PS-3 r-----+

PS-1

-15

§ 48VDC PS-4 15VDC

+15 8N28-1

~ § 48VDC SA036C Channel II Logic

& Terminations 8N26-2 PS-1

~~~3 §S-2 48 VDC PS-4 15 VDC L-__-"---+-'-'15---'

SA036E SA036B Terminations Channel IV Logic Terminations

~K5409 125 VDe I

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Cabinets 48 VDC Sorensen 15 VDC Sorensen

+/- 15 VDC SCI Module SA036C 8N26-2, PS-I 8N26-2, PS-2 8N26-2, PS3 & PS4 SA036D 8N26-1, PS-I 8N26-1, PS-2 8N26-1, PS3 & PS4 8N28-1, PS-I SA036E 8N26-1, PS-I 8N26-1, PS-2 8N26-1, PS3 & PS4 8N28-1, PS-I

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CALLAWAY PLANT RISK-INFORMED AMENDMENT REQUEST 24-HOUR BOP ESFAS COMPLETION TIME LAR Background WCAP-14333-P-A (TSTF-418-A)

SSPS Maintenance Completion Time (CT) extended from 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Callaway LA165 dated 1-31-05 (TAC No. MC1756)

BOP ESFAS - Function 6.c TS Table 3.3.2-1, Condition 3.3.2.0 OJ

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CALLAWAY PLANT RISK-INFORMED AMENDMENT REQUEST 24-HOUR BOP ESFAS COMPLETION TIME LAR Background

• SG low level (2/4 in 1/4 SG for MDAFP start, 2/4 in 2/4 SGs for TDAFP start)

• BOP ESFAS also processes ESF bus undervoltage inputs for TDAFP start

• Survey of PWROG stations - only Callaway and Wolf Creek have this TS Condition (WC pursuing digital modification fall 2012)

• 24-hour CT for one inoperable SSPS logic train inconsistent with immediate MODE 4 shutdown track for one inoperable logic train of BOP ESFAS

• 7300 channels have a 72-hour CT, SSPS trains have a 24-hour CT, MSFIS cabinets (SA075A/B) have a 6-hour CT but 1/3 PLCs in each train can be inoperable without Condition 3.3.2.S entry, LSELS cabinets (NF039A-C) have a 12-hour CT (see next figure), yet BOP ESFAS has no restoration CT

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CALLAWAY PLANT RISK-INFORMED AMENDMENT REQUEST 24-HOUR BOP ESFAS COMPLETION TIME BOP ESFAS AFAS (LO SG LVL Input Logic 2/4 on 1/4 CPIS and 2/4 on 214),

CRVIS SA03GA

,SA03GD FBIS CISA AFAS/SGBSIS UV and 2/4 SG low to SA03GC CRVIS SIS/CSAS To 'A' Trip &

'B' Bypass Bkrs START UV and 2/4 SG low DIESEL from SA036D SA0360 UV and 2/4 SG low T~~:W I r START from SA036E SSPS LOGIC

'A' Bypass Bkrs To 'B' Trip &

DIESEL I

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7300 Process Protection SIS/CSAS IV SSPS OUTPUT RELAYS I 8

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CRVIS Rel?y FWIS I'~I Testing CISA STC'B'

< LSA075B AFAS (LO SG LVL 2/4 on 1/4 and 2/4 on 2/4)

B 8 I FWlV's I SUV's I

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CALLAWAY PLANT RISK-INFORMED AMENDMENT REQUEST 24-HOUR BOP ESFAS COMPLETION TIME BOP ESFAS TS and Bases markups ESFAS Instrumenlation

xn+.~o", ol'\\ly (No cJ.-.."je.s" rnr'$.).)

3.3.2 Table ),3.2-1 (page 7 of 9)

Engineered safety Fe'lurs AduI!ion Syslem JI'lstnJmentatiO'n APPLICABLE MODES OR OlliER SPECIREO REQUIRED SURVEILLANCE AllOWtBlE FUNCTION CONOmoNS CHANNELS CONomONS REQUIREMENTS VAlUE'"

6.

Au:wIliary Feedwate,

a. Uanuallnitlatlon 1,2,3 "pump P

SR 3 3.2.8 NA

b. Automatic 1.2.3 2t1aios G

SR 3.3.2.2 NA Aduationlogic SR 3.3.2.4

.ndAt::tuation SR3.3.2.6 L

Relays (SSPS) 1,2,3

2lrtin, 0

SR 3.3.2 3 NA Autom.tic

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AdUition logic

.ndAclu.tlon

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d. SG'v\\Iatorlevel Low-Low

('l &18m t, 2, 3 4pel'SG 0

SR3.3.2,'

~ 2O.6%1~<<

Generator SR3.3.25

""_Range

'Na1erlevel SR 3.3.2 9 Instrl,l'fWll Low-low SR 3.3.2.10 SO'"

~~nt EnvirorvnentJ (21 Slum 1<01, ;z(r). 3{<)

4perSG 0

SRJ.3.2.1

~ 16.8%<QoI

~nelllllor SR 3.3.2.5 INIltr L......

SRJ.l.2.9 LOON-low SR 3.3.2.10

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(.) Th. AHowIibll VekJe defines the II"nlng safety system setlinq exoept for Functions 1.e, *.e.(1), S.c, 5.e.(1), 5.'.(2),

a.d.Cl),...,d 6 d.(2) Cthe NOITlftaI Trip $etpo1nt defines the Immg nfety system Mfting for these Functions). See Ihe Bill. for !he NCll'Tlln.II Trll5elPOnts.

(rl Except when the Cantairment Pressure - Environmental Alowanoe Modifier channels In the same prowcsion tilts ate

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(sl 1. ::ea:::~=r:n=.n::,,~:a~:t:af::=~~:':th~:~=~~=:~

~~~t!::~=I:i1,:r::c:'tiallr:e C:;~~~=blee~ channel setpolnll$ not conservative with respea to the

2. Tlle nmurMnt channel selpOint &hall be reset to 8value Ihl1ls within the as-NJft se~ 100000renoe btn<l on dtItf skte of the No~1 Trll SeCpajnt. or 10 a vatue mat Is IT'IOAl alnMrvatMI than the Nominal Trip setpoInt, other'*iSe.

the channellhall be dedirecl inoperable. The Non'Wtal T~ SetpcWQ and the methodology used 10 determlne the as-found leslaotliPtllnce aimia band tlnd the as-MItt secpokllloler8nce band shall be speotied n the 8Mes.

CALLAWAY PLANT 3.3-44 Amendment No. 189

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CALLAWAY PLANT RISK-INFORMED AMENDMENT REQUEST 24-HOUR BOP ESFAS COMPLETION TIME BOP ESFAS TS and Bases markups ESFAS Instrumentation 3.3.2 I

CONDITION REQUIRED ACTION COMPLETION TIME P.

One or more channel(s)

Inoperable.

Q One train inoperable.

.::INS"EJtt[ I R.

One or both train(s) inoperable.

P.1 Declare associated auxiliary feedwater pump(s) Inoperable.

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One train may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> tor surveillance testing provided the other train is OPERABLE.

~Q.:2.1 Be in MODE 3.

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~;2.:2.Be in MODE 4.

Immediately

~hOUrs

~hours

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R.1 Restore trein(s) to OPERABLE status.

OR 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> R.2.1 Be in MODE 3.

t.!ill 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> R.2.2 Be in MODE 4.

60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> INSERT 1 REQUIRED ACTION COMPLETION TIME Q.l Restore train to OPERABLE 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> status.

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CALLAWAY PLANT 3.3-32 Amendment No. 165

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CALLAWAY PLANT RISK-INFORMED AMENDMENT REQUEST 24-HOUR BOP ESFAS COMPLETION TIME BOP ESFAS TS and Bases markups ESFAS In.trumenlaOOn B3.3.2 BASES ACTIONS N 1 N 2 1 and N.2 2 (continued)

Condition N appfle.lo the Environmental A1low8nce Modifier (EAM) circuitry for the SG water Level-Low low \\rip Functions in MODES 1.2, and 3. With one or more EAM channel(s) inoperable. they must be placed in the tripped condition w~hin 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Placing an EAM channel in lrip automatically enables the SG V'later level - low low (Ad\\l8l'sa Containment Environment) bistable for that protec1ion channel, with ~

higher SG level Trip Setpoint (a higher trip setpoint means a feedwaler isolation or an AFWactuation would occur sooner). The Completion T~e of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> i. based on Reference 18. If lhe Inoperable channel cannot be placed in lhe tripped condrtion within the specified Completion Time.

the unit must be placed in a MODE where this Function is not required 10 be OPERABLE. The unit must be placed in MODE 3 within an additional six hours and in MODE 4 within the following six hours.

Oland 0 2 Condition 0 applies to the Auxiliary Feedwater Pump Suction Transfer on Suction Pressure - Low \\rip Function. The Condensate Storage Tank is the highly reliable and preferred.uction source for the AFW pumps. This function has a two--outooOf-three trip logic. Therefore. continued operation is allowed with one inoperable channel until the performance of the next monthly COT on one of the other channels, as long as the inoperable channel is placed in trip within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

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Condition P applies to the Auxiliary Feedwater Manual Initiation trip Function. The a**ocialed auxiliary feedwater pump(.) must be declared inoperable immediately when one or more channel(s) is inoperable.

Refer to LCO 3.7.5, "Auxiliary Feedwater (AiFW) System.'

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X1'JsEKr :S:::l.:l..Q Condition Q applies to lhe Auxiliary Feedwate~anceof Plant ESFAS automatic actuation logic and actuation relays, _tb on? 'FBi, iAQlI&lFSli1 the unil must be brought to MODE 3 withi¥OUrs and MODE 4 within oiIlQ~Iew;,,'~I!'ours. The Required Ac1ion are modified by a Note that allow. one lr to be bypassed for up to 2 rs for surveillance testing provided the ther train i. OPERABLE.

30 (continUed)

CALLAWAY PLANT B 3.3.2-52 Revision 8 INSERT 3.3.2.0 If one train is inoperable. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are allowed to restore the train to OPERABLE status. The 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> allowed for restoring the inoperable train to OPERABLE status is justified in Reference 23. The specified Completion Time is reasonable considering that there is another train OPERABLE, and the low probabilily of an event occurring during this interval. If the inoperable train cannot be restored to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,

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I, CALLAWAY PLANT RISK-INFORMED AMENDMENT REQUEST 24-HOUR BOP ESFAS COMPLETION TIME BOP ESFAS TS and Bases markups ESFAS Instrumentation B 33.2 BASES REFERENCES

17.

Lener from Mel Gray (NRC) to Gany L. Randolph (UE), "Revision (continued) 20 of the Inservice Testing Program for Callaway Plant, Unit 1 (lAC No. MA4469)," dated March 19, 1999.

18.

WCAP-14333-P-A, Revision 1, "ProbabUis1ic Risk Analysis of the RPS and ESFAS Test Times end Complelion TImes," October 1998.

19.

WCAP-15376-P-A, Revision 1, "Risk-Informe<l Assessment 01 the RTS and ESFAS Surveillance Test Intervals and Reactor Trip Breaker Tes1 and Completion Times," March 2003.

20.

'Neslinghouse Iener SCP-04-90 dated August 27, 2004.

21.

ULNRC-03748 date<l February 27,1998.

22.

IDP-ll-OOOll.

.23. C_II_WAV LiCMS'e /k.e.,ke;rf)(X)( J..Id.

I CALLAWAY PLANT B 3.3.2-S3 Revision 8

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CALLAWAY PLANT RISK-INFORMED AMENDMENT REQUEST 24-HOUR BOP ESFAS COMPLETION TIME PRA Model Discussion Current PRA Update for RG 1.200 Rev. 1 Peer Review F&O impacts One Significance Level A F&O, but flooding risk will be addressed in this BOP ESFAS LAR None of the 30 open Significance Level B F&Os have a demonstrable effect on the presented risk information.

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CALLAWAY PLANT RISK-INFORMED AMENDMENT REQUEST 24-HOUR BOP ESFAS COMPLETION TIME PRA Modeling Current Callaway PRA Model Includes Internal Events at Power Internal Flooding and Fire Modeling Under Development PRA Model Upgrade will Integrate Internal Flooding and Internal Fire Events into the Callaway PRA Similar approach used for ESW AOT amendment (i.e., areas screened out based on initiating event frequency or impact on AFW or ESW systems)

External Events Qualitatively addressed Similar approach used for ESW AOT amendment

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I CALLAWAY PLANT RISK-INFORMED AMENDMENT REQUEST 24-HOUR BOP ESFAS COMPLETION TIME Pr Inary egrated Risk Results The yearly risk contribution from a single T8 3.3.2 Condition Q 24-hour entry per year Risk Callaway Result Metric Acceptance Guidance Internal Flood Fire Total 7.205E-09 3.652E-09 5.478E-09 1.634E-8

.t>,CDF

<1 E-06 yr very small RG 1.174 2.466E-10 7.344E-12 1.102E-11 2.650E-10 6.LERF

<1 E-07 yr *1 - very small RG 1.174

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CALLAWAY PLANT RISK-INFORMED AMENDMENT REQUEST 24-HOUR BOP ESFAS COMPLETION TIME Preliminary Integrated Risk Results The yearly risk contribution based on plant experience, failure rate is 0.22 event/year Risk Metric Acceptance Guidance Internal 1.585E-09 Callaway Result Flood Fire 8.035E-10 1.205E-09 Total 3.594E-09 L\\CDF

<1 E-06 yr very small RG 1.174 5.425E-11 1.616E-12 2.424E-12 5.829E-11 L\\LERF

<1 E-07 yr very small RG 1.174

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CALLAWAY PLANT RISK-INFORMED AMENDMENT REQUEST 24-HOUR BOP ESFAS COMPLETION TIME Preliminary Integrated Risk Results

• The single event risk contribution (i.e., one T8 3.3.2 Condition Q entry with 24-hour Completion Time)

Callaway Result Risk Acceptance Guidance Metric Internal Flood Fire Total 7.205E-09 3.652E-09 5.478E-09 1.634E-8 ICCDP

<5E RG 1.177 2.466E-10 7.344E-12 1.102E-11 2.650E-10 ICLERP

<5E RG 1.177

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CALLAWAY PLANT RISK-INFORMED AMENDMENT REQUEST 24-HOUR BOP ESFAS COMPLETION TIME Meeting Conclusion Comments or Questions?

Concluding Remarks

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Mohan C. Thadani, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNrrLAJBurkhardt Resource RidsOgcRp Resource RidsRgn4MailCenter Resource GCasto, NRR/DSS/SBPB BlVlarcus, NRR/DE/EICB CDoutt, NRR/DLR/RER2 CTucci, NRR LTrocine, EDO RIV Summary: ML092730257

DORLlLPL4/BC DORLlLPL4/PM MMarkley MThadani 10/15/09 10/15/09