ML11137A003

Issuance of Amendments Regarding Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation

ML11137A003
Person / Time
Site:	Catawba
Issue date:	06/13/2011
From:	Jacqueline Thompson Plant Licensing Branch II
To:	Morris J Duke Energy Carolinas
Thompson J
References
TAC ME4863, TAC ME4864
Download: ML11137A003 (16)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 13, 2011 Mr. J. R. Morris Site Vice President Catawba Nuclear Station Duke Energy Carolinas, LLC 4800 Concord Road York, SC 29745

SUBJECT:

CATAWBA NUCLEAR STATION, UNITS 1 AND 2, ISSUANCE OF AMENDMENTS REGARDING TECHNICAL SPECIFICATON 3.3.2, "ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION" (TAC NOS. ME4863 AND ME4864)

Dear Mr. Morris:

The Nuclear Regulatory Commission has issued the enclosed Amendment No. 264 to Renewed Facility Operating License NPF-35 and Amendment No. 260 to Renewed Facility Operating License NPF-52 for the Catawba Nuclear Station, Units 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated September 16, 2010, as supplemented by letter dated March 31, 2011.

The amendments revise Technical Specification 3.3.2, "Engineered Safety Feature Actuation System (ESFAS) Instrumentation," to replace the references to the outdated logic per train per doghouse with updated references which reflect License Amendment Nos. 249 and 243 granted by the U.S. Nuclear Regulatory Commission staff on April 2, 2009.

A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

J. Morris

- 2 If you have any questions, please call me at 301-415-1119.

Sincerely, Jon Thompson, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-413 and 50-414

Enclosures:

1. Amendment No. 264 to NPF-35

2. Amendment No. 260 to NPF-52

3. Safety Evaluation cc w/encls: Distribution via Listserv

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 DUKE ENERGY CAROLINAS, LLC NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION DOCKET NO. 50-413 CATAWBA NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 264 Renewed License No. NPF-35

1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment to the Catawba Nuclear Station, Unit 1 (the facility) Renewed Facility Operating License No. NPF-35 filed by the Duke Energy Carolinas, LLC, acting for itself, and North Carolina Electric Membership Corporation (licensees), dated September 16, 2010, as supplemented by letter dated March 31, 2011, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

- 2

2.

Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-35 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 264

,which are attached hereto, are hereby incorporated into this renewed operating license. Duke Energy Carolinas, LLC, shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 90 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Gloria Kulesa, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to License No. NPF-35 and the Technical Specifications Date of Issuance: June 13, 2011

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS, LLC NORTH CAROLINA MUNICIPAL POWER AGENCY NO.1 PIEDMONT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 260 Renewed License No. NPF-52

1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment to the Catawba Nuclear Station, Unit 2 (the facility) Renewed Facility Operating License No. NPF-52 filed by the Duke Energy Carolinas, LLC, acting for itself, North Carolina Municipal Power Agency No.1 and Piedmont Municipal Power Agency (licensees). dated September 16, 2010, as supplemented by letter dated March 31, 2011, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (I) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable reqUirements have been satisfied.

- 2

2.

Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-52 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 260,which are attached hereto, are hereby incorporated into this renewed operating license. Duke Energy Carolinas, LLC, shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 90 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Gloria Kulesa, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to License No. NPF-52 and the Technical Specifications Date of Issuance: June 13, 2011

ATIACHMENT TO LICENSE AMENDMENT NO. 264 RENEWED FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 AND LICENSE AMENDMENT NO. 260 RENEWED FACILITY OPERATING LICENSE NO. NPF-52 DOCKET NO. 50-414 Replace the following pages of the Renewed Facility Operating Licenses and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Licenses Licenses NPF-35, page 4 NPF-35, page 4 NPF-52, page 4 NPF-52, page 4 TSs TSs 3.3.2-5 3.3.2-5 3.3.2-6 3.3.2-6 3.3.2-16 3.3.2-16

(2)

TechDic;@lSpeclficalions The Technical Specifications conlainedln Appendix A, as revised through Amendment No. 264Nhich are attached herelo, are hereby incorporated into this renewed opera illig license Duke Energy Carolinas, LLC shall operale Ihe facility in accordance with the Technical Specifications (3)

Updaled Final Safety Ana/'lSis ReDort The Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21(d), as revised on December 16,2002, describes certain future activtties to be completed before the period of extended operation. Duke shall complete these activities no later than December 6,2024, and shaH notify the NRC in writing when implementation of these activities is complete and can be verified by NRC Inspection The Updated Final Safety Analysis Report supplement as revised on December 16, 2002. described above. Shall be included in the nex1 scheduled update to Ihe Updated Final Safety Analysis Report required by 10 CFR 50.71 (e)(4). following issuance of this renewed operating license. Untillhal update is complete, Duke may make changes to the programs described in such supplement without prior Commission approval, provided that Duke evaluates each such change pursuant to the criteria setforth in 10 CFR 50.59 and otherwise compiles with the requirements in that section.

(4) Antltrust Conditions Duke Energy Carolinas, LLC shall comply with the antitrust conditions delineated In Appendix C to this renewed operating license.

(5) Fire Protection Prooram (Section 9.5 1, SER, SSER #2, SSER #3, SSER #4, SSER #5)"

Duke Energy Carolinas, LLC Shall implement and maintain In effect all prOvisions of the approved fire protection program as described in the Updated Final Safety Analysis Report. as amended. for the facility and as approved in the SER 1hrough Supplement 5, subject to the follOwing prOVision:

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes WOUld not adversely affect the ability 10 achieve and maintain safe Shutdown in i'1e event of a fire

-The parenthetical notallon follOWing lhe title of this renewed operating license condition denotes the section of the Safety Evaluation Report and/or ItS supplement wr.erein thIS renewed license condition is discussed Renewed License No. NPF-35 Amendment No 264

-4 (2)

T1JChng, SpPclttGlltiQna

,Tne T.dnc.I;S..,-Jfi.,t~nS ~ned Ir) AJ>>~ndli. A~ ~S ~ \\hnJugtl '..

Amtmdment Ng.2EO whir;:t! ~..u.ctwd'here1o*.,.. AI_.,~ted Into,(

~ I1tI'IOW'IMI opel"lMlg~. !Me E"""V7 c.ro"!'"lli. Lt.:C"";1I apanie' the

tlldily '".cc:cntance wIttI ~ T~ ~lon...'

, " '(31' *~ Ein,fseh.tv,.~:Re~* : ' "

,. 1M UpdatId FnI s.r.ty ~I RepGrt IUpplement ~ JIU!'i..nl to 10 CFR ~.21(d). a. nrwlled "" DaIambel ", ~2.*c:t1'lCtllel aMlin 'uU1t ICftYIUR '0..CXJh;plvlwd befor.t. PIIIod Qf ex1et K:hId.as*1IIM:IrL DuIW.'*II comptellt thea-8ctlVl1lea nO'...,..., F~ 24. 2028, lind lhel notify the NRC In _ling wtItn ~ or those.CUvt1l11 III. com..a..., '*' !:Ie

'VIt~ by NRC "petition, ThO uPdated.Flnlil S8Iaty AnIIIrtiI'.R8Pon Iupple"'l'm ** AIYIied 'on.,

December 'S. 2002. dIIIc:rIbId abow. lihld be tnGluc:tid In th' nexl.ChOduIec:l U", to the \\Jpdllted FMI SIIIely Aralyill R.~ requlrtd by,0 CFR 5O.11(.X4).I~ lnUIIIQ'of ttlia......c:t operati"U llalla.,Unal..,,

update

• complete. Dulle mlY ""ke crengn to lhe PI**'. cMaibed," 'Iuch aupplernent w\\fhoUl prior Comm!alun IIAX'OVii. provIIed tt.t DcIIat.ewlUldes

'.ch aLIen cMnge' p~ lo the atanI..l 1or'l1 In 10 CFR 50.59.

otherwls. ~ with the ntClU"""""ta in thai Hction.

III)

Anlb[yl1 Conditioi'll 0uQ t:nergy ~I. LlC aI;IIIII compty with !he anIIrus' ;gncJ\\IQnI deInRted in Appendhc C to till. roni'Mrd ~tnv.bn....

(5)

.FlntPNlectlon Pr9arOM(~ctlon9.5,1. SER, SSER'~. S$ERfI3. SSERM, SS.ER~"

Duk$ enetV)' Climtlnin. LlC.n.IIlmPlItmtmt lind m.....,...1n _lOt" PI'O'<ri1lon' of the appnMd nre ptOticIon pnI9I1IlI).' ~ In... Updalld FNI.SlltelY AnalyOl ~"...'amended; for I\\e teefllly'lIr'Id _.P~ In the SE~~

.~~t 5, aub)ect to IhIItolloM10 pmWalon:

. The llcen'" 'may m.kIt ctw'Igel 10 the fli,proVW1i in ;,..o1",1OIi p~

wlthol1l pnor ePPfOWI/ of Ihtt Commiw.lon* only 111h0M cr.naet would not advDraety _"act tile **tv 10 echt81111 WId maln'aln.1If".~ In the avent of 8 fInI.

"The.,..nlhlMlCBl nOl/lliOn 1011gwing the we of thlt r.,...,.g opre~Urv tiCem. condIIlQn denolellhe,ecuon ~ !he Sehtty EVlth.-tgn Report IIna/or ns.upplemel'llt wnaraln't'IIS rtIMWOd bnse ~I\\ion 1$ dim.lsaae2.

Renewed llcfmM No. NPF*52 Amendment No. 260

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME J.

One channel inoperable.

J.1 OR

• J.2

~-~--~-------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.

Place channel in trip.

Be in MODE 3.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 78 hours K.

One Main Feedwater K.1 Pumps trip channel inoperable.

OR Place channel in trip.

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

17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br /> (continued)

Catawba Units 1 and 2 3.3.2-5 Amendment Nos. 264, 260

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME L.

One channel inoperable.

L.1 OR L.2

---

NO TE------------

The 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.

Place channel in trip.

Be in MODE 3.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 12 hours (continued)

Catawba Units 1 and 2 3.3.2-6 Amendment Nos. 264, 260

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 4 of 5)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER NOMINAL SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT (2)

SG Water Level-High High (P-14) 4 per SG D

SR 3.3.2.1 SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 SR 3.3.2.9 SR 3.3.2.10

<;;85.6%

(Unit 1)

~ 78.9%

(Unit 2) 83.9%

(Unit 1) 77.1%

(Unit 2)

(3) Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements. See Item 5.b.(1) for Applicable MODES.

(4)

Tavg-Low 1.2(e) 4 J

SR 3.3.2.1 SR 3.3.2.5 SR 3.3.2.9

~ 56PF 564°F coincident with Reactor Trip, P-4 Refer to Function 8.a (Reactor Trip. P-4) for all initiation fUnctions and requirements.

(5)

Doghouse WaterLevel High High 1,2(e) 3 per train per doghouse L

SR3.3.2.S SR3.3.2.9 SR 3.3.2.12 s 12 inches above 577 ft floor level 11 inches above 577 ft floor level

6.

Auxiliary Feedwater

a.

Automatic Actuation Logic and Actuation Relays 1.2.3 21rains H

SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.6 NA NA

b.

SG Water Level

-Low Low 1,2.3 4 per SG D

SR 3.3.2.1 SR 3.3.2.5 SR 3.3.2.9 SR 3.3.2.10

~9%

(Unit 1) 235.1%

(Unit 2) 10.7%

(Unit 1) 36.8%

(Unit 2)

c.

Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

d.

Loss of Offsite Power 1,2.3 3 per bus D

SR 3.3.2.3 SR 3.3.2.9 SR 3.3.2.10 23242 V 3500 V

e.

Trip of all Main Feedwater Pumps 1,2 3 per pump K

SR 3.3.2.8 SR 3.3.2.10 NA NA

f.

AUxiliary Feedwater Pump Train A and Train B Suction Transfer on Suction Pressure - Low 1.2,3 3 per train M

SR 3.3.2.8 SR 3.3.2.10 A) ~ 9.5 psig B) ~ 5.2 psig (Unit 1)

5.0 psig (Unit 2)

A) 10.5 psig B) 6.2 psig (Unit 1) 6.0 psig (Unit 2)

(continued)

(e)

Except when all MFIVs, MFCVs, and associated bypass valves are closed and de-activated or isolated by a closed manual valve.

Catawba Units 1 and 2 3.3.2-16 Amendment Nos. 264, 260

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 264 TO RENEWED FACILITY OPERATING LICENSE NPF-35 AND AMENDMENT NO. 260 TO RENEWED FACILITY OPERATING LICENSE NPF-52 DUKE ENERGY CAROLINAS, LLC CATAWBA NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-413 AND 50-414

1.0 INTRODUCTION

By application dated September 16, 2010 (Agencywide Documents Access and Management System (ADAMS), Accession No. ML102660031), as supplemented by letter dated March 31, 2011 (ADAMS Accession No. ML110960432), Duke Energy Carolinas, LLC (Duke, the licensee), requested changes to the Technical Specifications (TSs) for the Catawba Nuclear Station, Units 1 and 2 (Catawba 1 and 2). The supplement dated March 31, 2011, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the U.S. Nuclear Regulatory Commission (NRC) staffs original proposed no significant hazards consideration determination as published the Federal Register on January 25, 2011 (76 FR 4384).

The proposed changes would revise the TS 3.3.2, "Engineered Safety Feature Actuation System (ESFAS) Instrumentation" to replace the references to the outdated logic per train per doghouse with updated references which reflect License Amendment Nos. 249 and 243 granted by the NRC staff on April 2, 2009.

2.0 REGULATORY EVALUATION

Section 182a of the Atomic Energy Act requires applicants for nuclear power plant operating licenses to include TSs as part of the license. The NRC's regulatory requirements related to the content of the TSs are contained in Title 10 of the Code ofFederal Regulations (10 CFR), Part 50, Section 50.36, "Technical specifications." The TS requirements in 10 CFR 50.36 include the following categories: (1) safety limits, limiting safety systems settings and control settings, (2) limiting conditions for operation, (3) surveillance requirements (SRs), (4) design features, (5) administrative controls, (6) decommissioning, (7) initial notification, and (8) written reports.

- 2

3.0 TECHNICAL EVALUATION

3.1 Proposed Change to TS 3.3.2, "ESFAS Instrumentation" The requested TS changes below (A - F) remove temporary changes that were previously reviewed and approved by the NRC on April 2, 2009 (Reference 1). Reference 1 revised the logic configuration for Function 5.b.(5), "Turbine Trip and Feedwater Isolation, Feedwater Isolation, Doghouse Water Level-High High," in Table 3.3.2-1, "Engineered Safety Features Actuation System (ESFAS) Instrumentation," to allow the licensee to modify the existing one out-of-one (1/1) logic per train per doghouse to a two-out-of three (2/3) logic per train per doghouse. The licensee requested the change to improve the overall reliability of this function and reduce the potential for spurious actuations.

Since the licensee was implementing this modification on a staggered basis during each unit's refueling outage, the NRC staff approved separate line items for each logic in TS Table 3.3.2-1, Function 5.b., item 5, for each logic (1/1 and 213). Thus, the previous amendment temporarily allowed both the logic configurations as the doghouse modifications were transitioned from a 1/1 to a 2/3 logic.

Both units have since completed the change to a 2/3 logic per train per doghouse. As a result, the 1/1 logic configuration is no longer applicable to either unit and needs to be removed.

Item G below is an additional change requested by the licensee to correct a text misalignment.

A.

Condition L: Delete Required Action L.1 B.

Condition L: Change L.2.1 to L.1 C.

Condition L: Change L.2.2 to L.2 D.

Condition L: Move the logical "OR" connector to left-most position E.

Condition L: Delete Note 1 under L.2.1 F.

Table 3.3.2-1, Function 5 Doghouse Water Level: Delete logic configuration section from Required Channels and Surveillance Requirements columns G.

Condition J: Move Completion Times up - align them with corresponding Required Actions 3.2 Summary The proposed changes are administrative changes that involve deleting obsolete requirements without affecting current technical content or current operational requirements. Additionally, the changes to a 2/3 logic per train per doghouse were previously approved in Reference 1. The remaining change proposed by the licensee is editorial in nature, involving reformatting. The NRC staff finds the proposed changes are acceptable.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the South Carolina State official was notified of the proposed issuance of the amendments. The State official had no comments.

-3

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change a requirement with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The NRC staff has determined that the amendments involve no significant increase in the amounts and no significant change in the types of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (76 FR 4384). The amendments also relate to changes in recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendments meet the eligibility criteria for categorical exclusions set forth in 10 CFR 51.22(c)(9) and (c)(10). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.

7.0 REFERENCES

1.

Letter J. Stang, NRC, to J. R. Morris, Duke Energy Carolinas, LLC, "Catawba Nuclear Station, Units 1 and 2, Issuance of Amendments Regarding Revision of the Technical Specifications (TSs) to Change the Logic Configuration of TS Table 3.3.2-1,

'Engineering Safety Feature Actuation System Instrumentation,' Function 5.b.(5),

Turbine Trip and Feedwater Isolation, Feedwater Isolation, Doghouse Water Level High High' (TAC NOS. MD9319 AND MD9320)" April 2, 2009 (ADAMS Accession No. ML090910863)

Principal Contributors:

K. Hemphill K. Bucholtz Date: June 13, 2011

ML11137A003

• via memorandum dated 1/5/11 ML103620308 OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA DIRS/ITSB/BC OGC NLO NRR/LPL2-11 BC NRR/LPL2-1/PM NAME JThompson MO'Brien RElliott*

LSubin GKulesa (PBoyle for)

JThompson DATE 05/26/11 05/26/11 115/11 06101/11 06/08/11 06/09/11