ML110400166

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Summary of Meeting with Union Electric Company to Discuss Licensee'S Planned Responses to Staff Requests for Additional Information Callaway Plant'S Request to Revise TS 3.3.2, ESFAS Instrumentation Functions
ML110400166
Person / Time
Site: Callaway Ameren icon.png
Issue date: 02/22/2011
From: Thadani M
Plant Licensing Branch IV
To:
Union Electric Co
Polickoski J, NRR/DORL/LPL4, 415-5430
References
TAC ME2822
Download: ML110400166 (18)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 22, 2011 LICENSEE: Union Electric Company FACILITY: Callaway Plant, Unit 1

SUBJECT:

SUMMARY

OF JANUARY 25, 2011, MEETING WITH UNION ELECTRIC COMPANY ON RESPONSES TO THE U.S. NUCLEAR REGULATORY COMMISSION STAFF'S QUESTIONS RAISED DURING THE PREVIOUS PUBLIC MEETING ON NOVEMBER 18, 2010 (TAC NO. ME2822)

On January 25,2011, the U.S. Nuclear Regulatory Commission (NRC) staff conducted a Category 1 public meeting with representatives of Union Electric Company, 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 responses to NRC staff questions raised during the previous public meeting on November 18, 2010, as noticed and summarized in the Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML103020279 and ML103470147 regarding Callaway Plant, Unit 1's license amendment request. The licensee requested revision to Technical Specification (TS) 3.3.2, "Engineered Safety Feature Actuation System (ESFAS) Instrumentation," in its submittal dated November 25,2009 (ADAMS Accession No. ML093290318). A list of attendees is provided in Enclosure 1.

The licensee first answered the three questions the NRC staff raised during the November 18, 2010, public meeting regarding (1) main feedwater flow actuation instrumentation for auxiliary feedwater (AFW); (2) the procedure for inserting the AFW ESFAS channel trip; and (3) the operational implementation interpretation of TS 3.3.2 as currently approved. The licensee also reviewed the main feedwater pump startup and shutdown procedures during plant power level manipulations. Finally, the licensee discussed its proposed TS 3.3.2 wording modification, provided within Enclosure 2, and the precedent for the proposal.

The NRC staff questioned the licensee's TS 3.3.2 modification proposal utilizing the TS proposal annotations provided in Enclosure 3. The staff discussed limits to the TS Limiting Condition for Operation (LCO) Completion Time based on the existing risk-informed analysis; the relevance of the licensee-discussed TS precedence to the proposed TS modifications; and the implication of a TS 3.0.2 exception due to the nature of the TS modification proposed.

Based on this discussion, the staff and licensee extensively examined the merits of various and specific TS 3.3.2 modifications.

The licensee expressed its intention to review the proposed changes internally and to provide an additional supplement to its license amendment request.

-2 No members of the public were in attendance. Public Meeting Feedback forms were not received.

Please direct any inquiries to me at 301-415-1476 or mohan.thadani@nrc.gov.

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 proposed TS wording modifications
3. NRC TS modification comments to licensee proposal cc w/encl: Distribution via Listserv

LIST OF ATTENDEES JANUARY 25, 2011, MEETING WITH UNION ELECTRIC COMPANY RESPONSES TO THE U.S. NUCLEAR REGULATORY COMMISSION STAFF'S QUESTIONS RAISED DURING THE PREVIOUS PUBLIC MEETING ON NOVEMBER 18,2010 DOCKET NO. 50-483 NRC

Participants:

Michael Markley, Chief, Plant licensing Branch IV Greg Casto, Chief, Balance of Plant Branch Mohan Thadani, Senior Project Manager, Plant Licensing Branch IV Andrew Howe, Senior Reliability and Risk Analyst, PRA Licensing Branch Carl Schulten, Senior Reactor Engineer, Technical Specifications Branch Stanley Gardocki, Reactor Systems Engineer, Balance of Plant Branch Kristy Bucholtz, Reactor Systems Engineer, Technical Specifications Branch Rossnyev Alvarado, Electronics Engineer, Instrumentation and Controls Branch James Polickoski, Project Manager. Plant Licensing Branch IV Union Electric Company

Participants:

Scott Maglio. Manager, Regulatory Affairs Bert Yates, Principal Engineer, Regulatory Affairs Mark Covey, Assistant Operations Manager, Operations Members of the Public:

None Enclosure 1

ENCLOSURE 2 LICENSEE PROPOSED TS WORDING MODIFICATIONS WITH BACKGROUND

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

COMPLETION CONDITION REQUIRED ACTION TIME I. One channel inoperable. ----------------- NOTE ----------------

The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing of other channels.

1.1 Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR 1.2 Be in MODE 3. 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> J. One e Main ------------------- NOTE ------------------

Feedwater pUI'1""ln"'-lrln channel{s) inoperable.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> OR J.2 Be in MODE 3.

CALLAWAY PLANT 3.3-29 Amendment No. 196

INSERT A2 CONDITION REQUIRED ACTION COMPLETION TIME J. One channel inoperable. ----------------NOTE--------------

One inoperable channel may OR 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 /> for surveillance testing of Two channels other channels.

inoperable within the ---------------------------------------

same separation group.

J.1 Place inoperable 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> channel(s) in trip.

OR J.2 Be in MODE 3. 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

COMPLETION CONDITION REQUIRED ACTION TIME to.iet !:Isee .. '.:ls;Qj ~

M.

w
.,

N.

One or more Containment N.1 Place channel(s) in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Pressure - Environmental Allowance Modifier OR channel(s) inoperable.

N.2.1 Be in MODE 3. 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> AND N.2.2 Be in MODE 4. 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br /> O. One channel inoperable. 0.1 Place channel in trip. ,.-1 R6t:lf  :;)4- Antir..r AND 0.2 Restore channel to During OPERABLE status. performance of the next required COT l continued}

CALLAWAY PLANT 3.3-31 Amendment No. 168

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

COMPLETION CONDITION REQUIRED ACTION TIME P. One or more channel(s) P.1 Declare associated Immediately inoperable. auxiliary feedwater pump(s) inoperable.

AND P.2 Declare associated Immediately steam generator blowdown and sample line isolation valve(s) inoperable.

Q One train inoperable. --------------- NOTE -----------------

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 /> for surveillance testing provided the other train is OPERABLE.

INsEI?TQ ...... --- ..----_.................... _--_ .. _-_ ..- ........_---------- ..

r&.+tQ. ::2./ Be in MODE 3. ~ours AN~

Q.2,.1 Be in MODE 4. d2 hours R. One or both train(s) R.1 Restore train(s) to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> inoperable. OPERABLE status.

OR R.2.1 Be in MODE 3. i 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> AND R.2.2 Be in MODE 4. 160 hours0.00185 days <br />0.0444 hours <br />2.645503e-4 weeks <br />6.088e-5 months <br /> (continued)

CALLAWAY PLANT 3.3-32 Amendment No. 197

INSERTC REQUIRED ACTION COMPLETION TIME Q.1 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.

I

~

No ~e~ - f17Vi;ld *r ~ ",,~ ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 8 of 11)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE(s)

6. Auxiliary Feedwater
a. Manuallniliation 1.2.3 1Ipump P SR3.3.2.8 NA
b. Automatic 1.2.3 2 trains G SR3.3.2.2 NA Actuation Log ie SR 3.3.2.4 and Actuation SR3.3.2.6 r

Relays (SSPS)

Automatic Actuation LogiC and Actuation Rela~(BOP ESF )

d. SG \/Vater Level Low-Low 1.2.3 2 trains Q SR 3.3.2.3 NA 1

(1) Steam 1.2.3 4 perSG D SR3.3.2.1 ~ 20.6%(1) of Generator SR3.3.2.S Narrow Range Water Level SR 3.3.2.9 Instrument Low-Low SR3.3.2.10 Span (Adverse Containment Environment)

(2) Steam 1(r),2(I),3(e} 4 per SG D SR3.3.2.1 ~ 16.6%(') of Generator SR3.S.2.5 Narrow Range water Level SR3.3.2.9 Instrument LOW-LOW SRS.S.2.10 Span

~ormal ontainment Environment)

(a) The Allowable value defines the limiting safety system setlin9 except for Functions 1.e, 4.e.(1). 5.c, 5.e.(1). 5.e.(2),

6.d.(1), and 6.d.(2) (the Nominal Trip SetpOint defines the limiting safety system setting for these Functions). See the Bases for the Nominal Trip Setpoints.

(r) Except when the Containment Pressure - Environmental Allowance Modifier channels in the same protection sets are tripped.

(s) 1. Ifthe as-found instrument channel setpOint is conservative with respect 10 the Allowable Value, but outside its as-found test acceptance criteria band. then the channel shall be evaluated to verify that it is functioning as required before returning the channel to servic&. If the as-found instrument channel setpeinl is not conservative with respect to the Allowable Value. the channel shall be declared inopenlble.

2. The instrument channel setpoint shall be reset to a value that is within the as-lefi seipoint tolerance band on either side of the Nornioal Trip Setpoint. or to a value that is more conservative than the Nominal Trip Setpolnt; otherwise.

the channel shall be declared Inoperable. The Nominal Trip Setpoints and the methodology used to determine the as-found test acceptance criteria band and the as-left setpoint tolerance band shall be specified in the Bases.

CALLAWAY PLANT 3.3-45 Amendment No. 197

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 9 of 11)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE(a)

6. Auxiliary Feedwater
d. SG Water Level Low-Low (3) Not used.

(4) Containment 1,2,3 4 N SR 3.3.2.1  !; 2.0 psig Pressure - SR3.3.2.5 Environmental SR3.3.2.9 Allowance SR 3.3.2.10 Modifier

e. Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.
f. Loss of Offsite 1,2,3 2 trains R SR3.3.2.7 NA Power SR 3.3.2.10
g. Trip of all Main Feedwater Pumps
h. Auxiliary Feedwater Pump Suction Transfer on Suction to' ~;,,)
l f}t;IMtt 3

~,

SR3.3.2.8 SR 3.3.2.1 SR 3.3.2.9 SR 3.3.2.10 SR 3.3.2.12

~

NA 20.64 psia Pressure* Low

)

(al The Allowable Value defines the limiting safety system setting except for Functions 1.e, 4.e.{l), 5.c, 5.e.(1), 5.e.(2).

6.d.(1). and 6.d.(2) (the Nominal Trip Setpoint defines the limiting safety system setting for these Functions). See the Bases for the Nominal Trip Setpoints.

(n) Trip function may be blocked just before shutdown of the last operating main feedwater pump and restored just after the first main feedwater pump is put into service following performance of its startup trip test.

(u) :::r::.NSEt<r E CALLAWAY PLANT 3.3*46 Amendment No. 197

INSERT E (u) Leo 3.3.2 is not applicable for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for the channels associated with placing the second main feedwater pump into service or when removing the first main feedwater pump from service.

AUCA 10-012. Revision 000 Attachment 1 Logic diagram of MDAFAS from trip of all Main Feedwater Pumps MfP'A' MfPS' MFP'A' FCPSL25 FCPSL012S FCIlS1.26 IV ArM 6Ignal61'1Om - - - - - ,

otIItr COI1d1l!oru; IltltDf O~ven AIlldliary F~pump

[ArM) 1 Note this drawing is simplified. Refer to J-104-00176 for the current design logic diagram Page 1 of2 Page 36 of 38

CALLAWAY PLANT RISK-INFORMED AMENDMENT REQUEST 24-HOUR BOP ESFAS COMPLETION TIME BOP ESFAS CRVIS Input SA036A Logic SA036D --

CPIS CRVIS FBIS AFAS/SGBSIS UV and 2/4 SG low to SA036C SIS/CSAS To 'A' Trip&

'B' Bypass Bkrs START Start TDAFW


1

~ SA036C

~

I__ ~

UV and from UV and 2/4 SG low SA036D 2/4 SG low DIESEL from SA036E START To 'B' Trip & DIESEL

'A' Bypass Bkrs NB02 UV SSPSLOGIC Relay SSPS OUTPUT RELAYS SLiSI ~ I SIS/CSAS B

CRVIS BLACKOUT SGBSIS FWIS Testing CPIS B EJ CISA CRVIS SA036B SA036E FBIS L

SA075B AFAS (LO SG LVL AFAS/SGBSIS 2/4 on 1/4 UV and 2/4 SG low

--~- and 214 on 214) Input Logic to SA036C

[ - FWlV's ISiNS I BOP ESFAS

~~ II~

~ r.4meren UC CiIIl:A~PIJi,

ENCLOSURE 3 NRC TS MODIFICATION COMMENTS TO LICENSEE PROPOSAL

EXAMPLE CONDITION REQUIRED ACTION COMPLETION TIME


NOTE--------------

One inoperable channel 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 /> for surveillance testing of other channels.

J. One channel J.1 Place channel in trip. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> inoperable.

M. Two channels M.1 Place channels in trip. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> inoperable.

AND AFW actuation on Trip of all Main Feedwater Pumps maintained.

EXAMPLE TABLE APPLICABLE MODES OR REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS VALUE(a)

OTHER CHANNELS REQUIREMENTS SPECIFIED

6. Auxiliary Feedwater
d. SG water level Low Low (3) not used.

(4) Containment 1, 2, 3 4 N SR 3.3.2.1 s 2.0 psig Pressure SR 3.3.2.5 Environmental SR 3.3.2.9 Allowance SR 3.3.2.10 Modifier

e. Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.
f. Loss of Offsite 1, 2, 3 2 trains R SR 3.3.2.7 NA Power SR 3.3.2.10
g. Trip of all Main 1, 2(ni J, M SR 3.3.2.8 NA Feedwater Pumps
h. Auxiliary  ;:: 20.64 psia Feedwater Pump Suction transfer on Suction Pressure Low (a) The allowable Value defines the limiting safety system setting foir Functions 1.e, 4.e.(1), 5.c, 5.e.(1), 5.e.(2),

6.d.(1), and 6.d.(2) (the Nominal Trip Set point defines the limiting safety setting for these Functions). See the Bases for the Nominal Trip Setpoints.

(n) Trip function may be blocked just before shutdown of the last operating main feedwater pump and restored just after the first main feedwater pump is put into service following performance of its startup trip test.

(u) During power ascension when one main feedwater pump is in operation supplying feedwater to the SGs and the other main feedwater pump is reset and not supplying feedwater to the SGs the following exception applies: The requirement for four operable channels is met if two required channels are OPERABLE on the associated main feedwater pump in operation supplying feedwater to the SGs and two required channels are in trip on the associated main feedwater pump in reset and not supplying feedwater to the SGs. When both main feedwater pumps are in operation supplying feedwater to the SGs the exception no longer applies.

- 2 No members of the public were in attendance. Public Meeting Feedback forms were not received.

Please direct any inquiries to me at 301-415-1476 or mohan.thadani@nrc.gov.

IRA!

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 proposed TS wording modifications
3. NRC TS modification comments to licensee proposal cc w/encl: Distribution via Listserv DISTRIBUTION:

PUBLIC RidsOgcRp Resource LPLIV r/f RidsOpaMail Resource RidsAcrsAcnw_MailCTR Resource RidsRgn4MailCenter Resource RidsNrrDorl Resource KBucholtz, NRR/DIRSIITSB RidsNrrDorlLpl4 Resource CSchulten, NRR/DIRSIITSB RidsNrrDirsltsb Resource AHowe, NRRIDRAIAPLA RidsNrrDraApla Resource SGardocki, NRRIDSS/SNPB RidsNrrDssSbpb Resource RAlvarado, NRRIDE/EICB RidsNrrDssSnpb Resource CSteger, NRR RidsNrrDeEicb Resource JTrapp, EDO RIV RidsNrrLAJBurkhardt Resource VDricks, OPA RIV RidsNrrPMCallaway Resource .IPolickoski, NRR ADAMS Accession No. Meetin Notice ML110120470 Meetin OFFICE DORLlLPL4/PM DORLlLPL4/PM DORLlLPL4/LA NAME JPolickoski MThadani MThadani DATE 2/9/11 2/16/11 2/22/11