ML14192B143

License Amendment Request to Revise Facility Operating License and the Technical Specifications to Incorporate Administrative Changes

ML14192B143
Person / Time
Site:	Peach Bottom
Issue date:	07/11/2014
From:	David Helker Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML14192B143 (20)

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10 CFR 50.90 July 11, 2014 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-277 and 50-278

Subject:

License Amendment Request to Revise Facility Operating License and the Technical Specifications to Incorporate Administrative Changes In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," Exelon Generation Company, LLC (EGC) requests an amendment to the Renewed Facility Operating License (FOL) Nos. DPR-44 and DPR-56 and the Technical Specifications (TS) for Peach Bottom Atomic Power Station (PBAPS),

Units 2 and 3, respectively.

The proposed amendment incorporates several administrative changes. The administrative changes consist of deleting License Condition 2.C(13} since it was a one-time commitment which has already been fulfilled, removing an Operating License Footnote that is not required (PBAPS Unit 3 only), correcting the site area boundary figure, and removing Core Operating Limits Report (COLR) references that are no longer applicable. Attachment 1 provides a description of the proposed changes. Attachment 2 provides the existing FOL and TS pages marked up to show the proposed changes.

There are no regulatory commitments contained in this letter.

The proposed changes have been reviewed by the PBAPS Plant Operations Review Committee and approved by the Nuclear Safety Review Board in accordance with the requirements of the EGC Quality Assurance Program.

EGC requests approval of the proposed amendment by July 11, 2015. Once approved, the amendment shall be implemented within 60 days of issuance.

U.S. Nuclear Regulatory Commission LAR Revise the FOL and TS to Incorporate Administrative Changes July 11, 2014 Page2 In accordance with 10 CFR 50.91, "Notice for public comment; State consultation,"

paragraph (b), EGC is notifying the Commonwealth of Pennsylvania of this application for license amendment by transmitting a copy of this letter and its attachments to the designated State Official.

If you have any questions or require additional information, please contact Stephanie J.

Hanson at (610) 765-5143.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 11th day of July 2014.

Respectfully, David Helker Manager, Licensing and Regulatory Affairs Exelon Generation Company, LLC Attachments: 1. Evaluation of Proposed Changes

2. Markup of Facility Operating License and Technical Specifications Pages cc: USNRC Region I, Regional Administrator USNRC Project Manager, PBAPS USNRC Senior Resident Inspector, PBAPS R. R. Janati, Bureau of Radiation Protection S. T. Gray, State of Maryland

ATTACHMENT 1 Evaluation of Proposed Changes Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 Docket Nos. 50-277 and 50-278

Subject:

License Amendment Request to Revise the Facility Operating License and the Technical Specifications to Incorporate Administrative Changes 1.0

SUMMARY

DESCRIPTION 2.0 DETAILED DESCRIPTION

4.0 REGULATORY EVALUATION

4.1 Applicable Regulatory Requirements/Criteria 4.2 Precedent 4.3 No Significant Hazards Consideration 4.4 Conclusions

6.0 REFERENCES

License Amendment Request Attachment 1 Revise the FOL and TS to Incorporate Administrative Changes Page 1of5 Evaluation of Proposed Changes Docket Nos. DPR-44 and DPR-56 1.0

SUMMARY

DESCRIPTION In accordance with 1o CFR 50.90, "Application for amendment of license, construction permit or early site permit," Exelon Generation Company, LLC (EGC) is requesting an amendment to the Renewed Facility Operating License (FOL) Nos. DPR-44 and DPR-56 and the Technical Specifications (TS) for Peach Bottom Atomic Power Station (PBAPS) Units 2 and 3, respectively.

The proposed amendment incorporates several administrative changes. The administrative changes consist of deleting license condition 2.C(13) since it was a one-time commitment which has already been fulfilled, removing an Operating License Footnote that is not required (PBAPS Unit 3 only), correcting the site area boundary figure, and removing Core Operating Limits Report (COLR) references that are no longer applicable. Attachment 1 provides a description of the proposed changes. Attachment 2 provides the existing FOL and TS pages marked up to show the proposed changes.

2.0 DETAILED DESCRIPTION The following proposed changes to the PBAPS, Units 2 and 3, FOL and TS, summarized below, are administrative in nature:

1. Footnote "1" and its associated reference on Page 3 of the PBAPS, Unit 3 Operating License, pertaining to the licensed power level in association with Amendment No. 250 is being deleted in its entirety.

2. License Condition 2.C(13) on pages 7 and 7a of the PBAPS Operating License, concerning the implementation of Amendment Nos. 264 and 268, which is the adoption of TSTF-448, Revision 3, pertaining to the determination of control room envelope (CRE) unfiltered air inleakage is being deleted in its entirety.

3. TS Figure 4.1-1, on page 4.0-3, titled "Site and Exclusion Area Boundaries", for PBAPS, is being revised to correct an error on the figure.

4. References 2 through 9 contained in TS Section 5.6.5.b, on pages 5.0-21 and 5.0-22, for PBAPS, are being removed in their entirety.

Markups of the proposed administrative changes are provided in Attachment 2.

3.0 TECHNICAL EVALUATION

PBAPS Unit 3, Page 3 - Operating License Footnote "1" and its associated reference on page 3 of the PBAPS, Unit 3 Operating License, pertaining to the licensed power level is being proposed for deletion. This one-time commitment was originally added to the PBAPS, Unit 3 Operating License as part of Amendment No. 250 to allow for implementation of the Measurement Uncertainty Recapture (MUR) power uprate following the Fall 2003 Refueling Outage. The intent of the commitment was to indicate future implementation. This commitment was implemented upon startup following the Fall 2003 refueling outage. This footnote is no longer necessary and therefore, proposed for deletion.

License Amendment Request Attachment 1 Revise the FOL and TS to Incorporate Administrative Changes Page 2 of 5 Evaluation of Proposed Changes Docket Nos. DPR-44 and DPR-56 License Condition 2.C(13)- Control Room Habitability PBAPS, Units 2 and 3, License Condition 2.G{13) states that upon implementation of Amendment Nos. 264 and 268, respectively, which is the adoption of TSTF-448, Revision 3, the determination of control room envelope (GRE) unfiltered air inleakage as required by SR 3.7.4.4, in accordance with TS 5.5.13.c(i), the assessment of CRE habitability as required by Specification 5.5.13.c(ii) and the measurement of CRE pressure as required by Specification 5.5.13.d, shall be considered met. Amendment Nos. 264 and 268 were implemented on August 29, 2007, as stated above. The surveillance, assessment and measurement were considered met upon implementation and the first performances were subsequently performed within the allowance of the operating license. License Condition 2.C(13} is no longer necessary and therefore, proposed for deletion.

TS Figure 4. 1 Site and Exclusion Area Boundaries It is proposed to revise PBAPS TS Figure 4.1-1, Site and Exclusion Area Boundaries, to correct an error in the figure. The correction includes revising the location of Lay Road, specifically, the details pertaining to the main access road in relation to the PBAPS facility. Additionally, the figure has been revised to adjust the details of the parking areas, correct the access road within the Site Area Boundary (SAS), and change the Susquehanna River label to Conowingo Pond.

The route of Lay Road has not physically changed, nor has the location of the SAB changed.

Once within the SAS, the access road runs along the bank of the Conowingo Pond. Extra lines that depict old parking areas were removed from the drawing. Additionally, the large body of water on this portion of the Susquehanna River that provides cooling water to the PBAPS site is called the Conowingo Pond in the UFSAR. Finally, the railroad tracks have been removed as they were there during the construction phase of PBAPS and no longer in place.

TS Section 5.6.5.b- COLR References It is proposed to revise PBAPS TS Section 5.6.5.b to remove references that are no longer valid methodologies for determining Core Operating Limit Reports (COLA) values. TS Section 5.6.5.b, References 3 through 8 approved in the 1988 time frame are no longer used. In the 2001 time frame, EGG terminated the capability to perform analysis using these referenced methodologies. Furthermore, References 2 and 9 can also be administratively deleted.

Reference 2 is an application report, not a methodology. The ARTS/MELLLA licensing basis is documented directly in GESTAR (TS Section 5.6.5.b, Reference 1). Reference 9 was added when PBAPS implemented the long term stability solution. This methodology licensing topical report (LTR) is now referenced within GESTAR (TS Section 5.6.5.b, Reference 1) and no longer needs to be referenced separately in the TS.

4.0 REGULATORY EVALUATION

4.1 Applicable Regulatory Requirements I Criteria 10 CFR 50.36, "Technical specifications," details the information that must be included in each station's TS. 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," permits a holder of a license to request the NRG to amend the license by fully describing the changes desired. The proposed changes are intended to keep the Facility Operating Licenses and Technical Specifications current by deleting obsolete information.

License Amendment Request Attachment 1 Revise the FOL and TS to Incorporate Administrative Changes Page 3 of 5 Evaluation of Proposed Changes Docket Nos. DPR-44 and DPR-56 Appropriate bases are provided to support removing the obsolete information from the Facility Operating Licenses and Technical Specifications.

The proposed changes incorporate several administrative changes that include correcting an error in a figure and other inconsistencies. The proposed changes have no impact on current Safety Limits, Limiting Safety System Settings, Limiting Control Settings, Limiting Conditions for Operation, Surveillance Requirements, Design Features, or Administrative Controls. Therefore, EGC concludes that the methods used to comply with 10 CFR 50.36 and 10 CFR 50.90 are not modified by the proposed changes, and the requirements continue to be met.

Historically obsolete information and inconsistencies that have no safety impact have been introduced into the PBAPS FOL and TS. The purpose of this amendment request is to correct those inconsistencies and errors. The proposed changes do not involve any physical changes to the structures, systems, or components (SSCs) in the plant or the way the SSCs are operated or controlled. None of these changes are of a technical nature and they do not require a technical analysis.

4.2 Precedent None 4.3 No Significant Hazards Consideration In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," Exelon Generation Company, LLC (EGC) is requesting an amendment to the Renewed Facility Operating License (FOL) Nos. DPR-44 and DPR-56 and the Technical Specifications (TS) for Peach Bottom Atomic Power Station (PBAPS) Units 2 and 3, respectively.

The proposed amendment incorporates several administrative changes. The administrative changes consist of deleting License Condition 2.C(13) since it was a one-time commitment which has already been fulfilled, removing an Operating License Footnote that is not required (PBAPS Unit 3 only), correcting the site area boundary figure, and removing Core Operating Limits Report (COLR) references that are no longer applicable. EGC has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:

1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No.

No physical changes to the facility will occur as a result of this proposed amendment. The proposed changes will not alter the physical design or operational procedures associated with any plant structure, system, or component. The proposed changes are administrative in nature and have no effect on plant operation.

Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.

License Amendment Request Attachment 1 Revise the FOL and TS to Incorporate Administrative Changes Page 4 of 5 Evaluation of Proposed Changes Docket Nos. DPR-44 and DPR-56

2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No.

The proposed changes are administrative in nature. The proposed changes do not alter the physical design, safety limits, or safety analysis assumptions associated with the operation of the plant. Accordingly, the changes do not introduce any new accident initiators, nor do they reduce or adversely affect the capabilities of any plant structure, system, or component to perform their safety function.

Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.

3. Does the proposed change involve a significant reduction in a margin of safety?

Response: No.

The proposed changes conform to NRC regulatory guidance regarding the content of plant Technical Specifications. The proposed changes are administrative in nature. The proposed changes do not alter the physical design, safety limits, or safety analysis assumptions associated with the operation of the plant.

Therefore, the proposed changes do not involve a significant reduction in a margin of safety.

Based on the above, EGC concludes that the proposed amendment does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of no significant hazards consideration is justified.

4.4 Conclusions In conclusion, based on the considerations discussed above: (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 amendment will not be inimical to the common defense and security or the health and safety of the public.

5.0 ENVIRONMENTAL CONSIDERATION

The proposed amendment is confined to (i) changes to surety, insurance, and/or indemnity requirements; (ii) changes to recordkeeping, reporting, or administrative procedures or requirements; (iii) changes to the licensee's or permit holder's name, phone number, business or e-mail address; (iv) changes to the name, position, or title of an officer of the licensee or permit holder, including but not limited to, the radiation safety officer or quality assurance manager; or (v) changes to the format of the license or permit or otherwise makes editorial, corrective or other minor revisions, including the updating of NRC approved references.

Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(10). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.

License Amendment Request Attachment 1 Revise the FOL and TS to Incorporate Administrative Changes Page 5 of 5 Evaluation of Proposed Changes Docket Nos. DPR-44 and DPR-56

6.0 REFERENCES

1. Letter from J. P. Boska (U.S. Nuclear Regulatory Commission) to J. L. Skolds (Exelon Generation Company, LLC), Peach Bottom Atomic Power Station, Units 2 and 3-lssuance of Amendments RE: 1.62% Increase in License Power Level (TAC NOS.

MB5192 and M85193) dated November 22, 2002.

2. Letter from C. Gratton (U.S. Nuclear Regulatory Commission) to C. G. Pardee (Exelon Generation Company, LLC}, Byron Station, Unit Nos. 1 and 2; Braidwood Station, Units 1 and 2; Clinton Power Station, Unit No. 1; LaSalle County Station, Units 1 and 2; Limerick Generating Station, Units 1 and 2; and Peach Bottom Atomic Power Station, Units 2 and 3 - Issuance of Amendments Regarding the incorporation of TSTF-448, Revision 3, "Control Room Habitability" (TAC Nos. MD5272, MD 5273, MD5270, MD5271, MD5274, MD5277, MD5278, MD5279, MD5280, MD5282, and MD5283) dated October 31 , 2007.

3. U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, NUREG-1433, Revision 4, "Standard Technical Specifications - General Electric BWR/4 Plants,"

dated April 2012.

4. 10 CFR 50.36, Technical specifications.

ATTACHMENT 2 Markup of Facility Operating License and Technical Specifications Pages Peach Bottom Atomic Power Station Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 Docket Nos. 50-277 and 50.278 REVISED FACILITY OPERATING LICENSE & TECHNICAL SPECIFICATIONS PAGES (MARK-UPS)

Unit 2 FOL and TS Pages FOL Page 7 FOL Page 7a 4.0-3 5.0-21 5.0-22 Unit 3 FOL and TS Pages FOL Page 3 FOL Page 7 FOL Page 7a 4.0-3 5.0-21 5.0-22

(11) Mitigation Strategy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

(a) Fire fighting response strategy with the following elements:

1. Pre-defined coordinated fire response strategy and guidance

2. Assessment of mutual aid fire fighting assets

3. Designated staging areas for equipment and materials

4. Command and control

5. Training of response personnel (b) Operations to mitigate fuel damage considering the following:

1. Protection and use of personnel assets

2. Communications

3. Minimizing fire spread

4. Procedures for implementing integrated fire response strategy

5. Identification of readily-available pre-staged equipment

6. Training on integrated fire response strategy

7. Spent fuel pool mitigation measures (c) Actions to minimize release to include consideration of:

1 . Water spray scrubbing

2. Dose to onsite responders (12) The licensee shall implement and maintain all Actions required by Attachment 2 to NRC Order EA-06-137, issued June 20, 2006, except the last action that requires incorporation of the strategies into the site security plan, contingency plan, emergency plan and/or guard training and qualification plan, as appropriate.

tt.at ~~ef Amern:lmem-Ne~2@4 aaop~

R&~,the-1etefmi-Aatiefl...-0f eentrol r~e (CRE) unfilterea a+r

~e as required by SR 3.7.4.4, in aooordanee witl:l TS 5.5.13.c(i), tl:le assessment of CRE 11abitabi!ity as required by Speeifioation 5.5.13.c(ii),

a-Ad tl1e measurement-ef CRE pressure a~e~GR

&,.e.13.d, shall be consi~. i;;ollowffig implementation:

(at ~-SR 3.7.4.4-,,,,*in aceerctanse-wi-tR

~fi-Gatie-A~5.a.13.o(~}-,-~i3&w~in the spesified Frequency of 6 yeaFs, f>lus the 18-mentl:i all-e\Nance ef SR 3.0.2, as measured from Oeto-SeF 25, 2Q04, tAe Gate of the most recent-successful traeer-~ed-in tl:ie January 21, 2005-ietteF,fesponse to Generic Letter 2003 01, er--within t~*{he tinie period since the most recent sucoessful tracer gas test is greateF tl:lan 6 years.

Renewed License No. DPR-44 Revised by letter dated August 9, 2007 Amendment 264 Page 7

(b) The f1fst.performanee of th&-i)eri-0dic assessmen}-ef-GRE habitabtl~ty, Spoo~fo.:;ation SA>:43.c(ii}, -sflall bewithin-3 years,-pk:Js the-9-montA-allswance et: SR* 3,0,2,as-ffiees1:1reel-ffemGetetlef-25, 2-0()4.,. . the-Gat.a-of**the-me.stFeeeRt-ffi:lcessful-tfaeer*gas-test,*as statOO-ln-the Jamiafj' 2:t-,2ooe-letterr-espense ta-Generic t.-etter 2003-~rwitnm-the next-9-montA:s iHfl.e*time perioo sinc~tt-le mest-*receAt-soocessflll-tfaeFgas-test*is-greater-than+year-s; (s1 The.f~fSt-perforrnanee ofthe-*periodic measurement-ef GHE pressuf&;-Sf}ecifieati-On5,&.-:t-&.41-shaH-be-within**24-menthslf:llUS tRe-180.-days-altowed-by-SR-3:0.2, as measured from-the-date-ef the-mest.FeBefrt....sueeessfHl..presStJfe-measl:lfefflel'lt-test-;-ef-WtthiR 180 days-if not peffermed f*'6Viously

( 14) Spent Fuel Pool Criticality Considerations (a) Use of spent fuel pool storage cells without NETCO-SNAP-IN rack inserts shall be restricted as follows:

1) Minimum panel Boron-10 areal density of a storage cell shall be greater than or equal to 0.014 grams per square centimeter to store fuel assemblies with the maximum in-core cold k-infinity of up to 1.235. The minimum panel Boron-10 areal density shall be evaluated by assuming that the panel areal density was initially equal to a value of 0.0235 grams per square centimeter.

2) A storage cell shall not contain any fuel assembly if the minimum panel Boron-10 areal density of a storage cell is less than 0.014 grams per square centimeter. The minimum panel Boron-10 areal density shall be evaluated by assuming that the panel areal density was initially equal to a value of 0.0235 grams per square centimeter.

(b) Until the installation of NETCO-SNAP-IN rack inserts are completed in the Peach Bottom Unit 2 spent fuel pool, Boraflex degradation shall be monitored analytically every 6 months.

(c) Boraflex degradation shall be monitored by in-situ testing in the Peach Bottom Unit 2 spent fuel pool no later than December 31, 2014, unless installation of the NETCO-SNAP-!N rack inserts for Unit 2 have been completed prior to this date.

(d) Installation of NETCO-SNAP-IN rack inserts shall be completed by December 31, 2016.

Renewed License No. DPR-44 Revised by letter dated August 9, 2007 Amendment No. 287 Page 7a

Design Features 4.0 Figure 4.1-1 (page 1 of 1)

Site and Exclusion Area Boundaries PBAPS UNIT 2 4.0-3 Amendment No.

l<l:'pur ting lzequ i rernen ts 5.6 Ci

• 6 Rep u r' t i ng I< e q u *j re rn en t s ( con L i nu e 'i) 5.6.5 .CJIBL_S}JJERATI~H;_J IMITS fff PQRT lUllB.l

a. Co1-e uperating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, cH1d shall b1:: doc1m1c'nted in U1e COLI\ for the following:

1. The Average Planar Linear Heat Generation Rate for Specification 3.2.1;

2. The Minimum Critical Power Ratio for Specifications 3.2.2 and 3.3.2.1;

3. The Linear Heat Generation Rate for Specification 3.2.3;

4. The Control Rod Block Instrumentation for Specification 3.3.2.l; and

5. The Oscillation Power Range Monitor (OPRM)

Instrumentation for Specification 3.3.1.1.

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents-:

1. NEDE-24011-P-A, "General Electric Standard Application for Reactor Fuel" latest approved version as specified in the COLR)~ I

-* Nf{}G--3--2--162-P-;-!!Ma->(i-ffitttl

l--f>~*t-eftEJ.eEl--l::-EraEl-1::4-He-l::-itn+-t-and---A-Rf-S

+/--mj3-reverne!Tt--P-rog-ra-m---Afta-l-y-&e-5-f.or--*-Pea-e-A--*B-0Hf}f!l-A-tom-:i-e Power--&t-a-t-i-en-tJtri-ts- -a+t&--3,-~'---R-e-v-i-5 i on--21 ---March,--+/-*9-9 5 ;-

'.h- P-Et-e-F-M-S--8-8-W--*A-;---..!!-S-t-e-ady--St-at-e--+*hePfflirl..-Hy*dr-a-tt.+4-e-Afra-i-y-s+s-e-f.-P-eac.fl--&e+l::om--lJfl-4-t-s-2--afl-Ei-3---u-si-A-§-'1;+1-e-..f+&Wfl:

Gomput-e-r-Gode~

+.-* P-EC-e-FM.S*--OOB-2--A-;**-*!44-effioEJ--.f-e-r--&a+c-tt-l-a-t4-Ag--T-P~Ht C-H-Hea l Po~" e r-Ra-t-4-B-s-fer- *Bo i l i n-g--w-a-t-ef---R-e*a-et-e-r *<***R*ET**R-AN-+Gf'P.fG-e--~-

5-:- Pf.fe-FM&* tJ.oo.3--A.,----!!..£t-e-aEl-y*-&t-a-t-e--Ft:te+-fl.-e-r-*f-*e-rm a n c e Me-tlte4&

R-ei'T&f-*t..!!--;*

6,- .P*E*G*o****..f.MS.--0-00-4--A,--..!*~M-ethe-d-s-for*P-ef'-f-.e*rmi**~WR Sys-t-e11t5-H>-a-fl-s-i-e-n t An a l-y-s+~

continued PBAPS UN IT 2 5.0-21 Amendment No. 251

Repor't i ng f\eyui remen Ls 5.6

~.6 Reµorting keyuirements

'). 6. 5 CORF_OeERATULCi UMITS _REPORT (COLR) (continued)

+. Pft.e--.-fHS-~-A,---~ods-*-fe.-!:>--P-er--f-G-Fffi4-Rg--B~~-R-&t-eady--

S*ta**te---Re-a-c*t* o*r--P-ft.y-s*i***C*S******Ana-+ys-i***S**~

&... P-f.fe-FMS-*-00-06---A-,--~'..f4e*HH:H:f-s-..f&f-P*e*r-f-&fffri-A-g---&W-R-R-e-l--oa-d

-s-a+e-ty--E*v-a-i-t:ta-tA**O*tl5*!!-;-a-nEI-9,- Nl::-D0--3-2-4-6-5-***A*; ..!!.Re-tr-et*o*r**-&t-a-b..:i*l+t~*teet-a-n-fr-*Sup-f:H'e-5 S.&k:1-t-+0+ts-l::+e-e-r1-s-i ~s-i-s--f4e-t-fl-O-Elo..:J-019-y-An-El--*R e l oad AfrfH+c-at-i-~---A-u~J:..9-9-6-;-

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems CECCS) limits, nuclear limits such as SOM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR, including any midcycle rev1s1ons or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.6.6 Post Accident Monitoring (PAM) Instrumentation Report When a report is required by Condition B or F of LCO 3.3.3.1, "Post Accident Monitoring (PAM) Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

5.6.7 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT CPTLR)

a. RCS pressure and temperature limits for heatup, cooldown, low temperature operation, criticality, and hydrostatic testing as well as heatup and cooldown rates shall be established and documented in the PTLR for the following:

i) Limiting Conditions for Operation Section 3.4.9, "RCS Pressure and Temperature CP/T) Limits" ii) Surveillance Requirements Section 3.4.9, "RCS Pressure and Temperature CP/T) Limits" (continued)

PBAPS UN IT 2 5.0-22 Amendment No. 286

(5) Exelon Generation Company, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not to separate, such byproduct and special nuclear material as may be produced by operation of the facility, and such Class B and Class C low-level radioactive waste as may be produced by the operation of Limerick Generating Station, Units 1 and 2.

C. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 of Part 50, and Section 70.32 of Part 70; all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:

(1) Maximum Power Level Exelon Generation Company is authorized to operate the Peach Bottom Atomic Power Station, Unit No. 3, at steady state reactor core power levels not in excess of 3514 megawatts thermal.

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 294, are hereby incorporated in the license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications. 1 (3) Physical Protection Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the au hq!'.!ty of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set o p ~submitted by letter dated May 17, 2006, is entitled: "Peach Bottom Atomic Power Station Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program, Revision 3." The set contains Safeguards Information protected under 10 CFR 73.21.

Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP),

including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54{p). The Exelon Generation Company CSP was approved by License Amendment No. 283.

~ power level was revised by Amendment No. 250, dated November 22, 2002, and *.viii be implemented following the 44t'- refueling outage currently scheduled for Fall 2-003:

~ rhe training and Qualification Plan and Safeguards Contingency Plan and Appendices to the Security Plan.

Renewed License No. DPR-56 Revised by letter dated October 28, 2004 Revised by letter dated November 5, 2004 Revised by letter dated May 29, 2007 Amendment No. 294 Page 3

plant-specific program. Before July 2, 2014, the licensee will notify the NRC of its decision to implement the core shroud inspection and evaluation guidelines program or a plant-specific program, and provide the appropriate revisions to the Updated Final Safety Analysis Report Supplement summary descriptions of the core shroud inspection and evaluation guidelines program.

(11) Mitigation Strategy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

(a) Fire fighting response strategy with the following elements:

1. Pre-defined coordinated fire response strategy and guidance

2. Assessment of mutual aid fire fighting assets

3. Designated staging areas for equipment and materials

4. Command and control

5. Training of response personnel (b) Operations to mitigate fuel damage considering the following:

1. Protection and use of personnel assets

2. Communications

3. Minimizing fire spread

4. Procedures for implementing integrated fire response strategy

5. Identification of readily-available pre-staged equipment

6. Training on integrated fire response strategy

7. Spent fuel pool mitigation measures (c) Actions to minimize release to include consideration of:

1. Water spray scrubbing

2. Dose to onsite responders (12) The licensee shall implement and maintain all Actions required by Attachment 2 to NRC Order EA-06-137, issued June 20, 2006, except the last action that requires incorporation of the strategies into the site security plan, contingency plan, emergency plan and/or guard training and qualification plan, as appropriate.

E+at LJp~leffieAtatieFH>f~ent Ne. 238 ade13t}Ag +s+i;;: 448, Revfs.ie~eterminatien ef oentrol reom envelepe (GRE) unfiltered air iflleakage as required by SR 3.7.4.4, in aooordanoe with +S 5.5.13.c(i), the assessmeA-1:-ef GRE R-ae#abi#t'f"as fequireE!-by Specificatien 5~~

and the mea&UfeFRe~iJ'FBSSUfe-a&fequired .&~#k~ahefl 5.5.13.d, shall be considered met. F-ollowing im13lementatien:

{-0}  :+he-t:if . . . , in accenfance wit{:}

Specificatien 5.5.13.c(i), shall ee Nithin tt:le speoifieel Frequefloy sf 1

@ yeaFS, plus the 18 menth allewaAoe ef SR 3.0.2, as measures fF~~5, 2004, the elate ef4he most resent successM Renewed License No. DPR-56 Revised by letter dated August 9, 2007 Amendment No. 268 Page 7

traeer:-gastest-,-as-st-ated-ifl-theJ.anuafY-21,-2-005-letteFfeSJ30Rse-to Gener-icrLetter-2003-04,-0r-witt-llfl****the**n&l<t*4S-meffihs-tf-the*time per1od-sirn3e*the*most-reeeAt-sueeessf-ul-traeef*-gas-tesHs-great-ef than..0-*years:

(a) T-he-*-fifst--perler-mance-ef--the--periedfe-assessffient*-ef.-*GRE haBitabiltty,&peeifi.eation-&:&-1-3,e(fi};-shal~-De-witt-tin--3-years,-plus the-9-month--allewanee-ef.*SR-~Hl-2,-as-meas1:1rea-fr-0m-Gctooer-2§.,

20G4,the-*dateef themest--rewAt--s1:J.GeessfuHraeer-gas-testr-as stated-in-the-January-24T200a--1-0tter-respensete--Gener-is-Letter 2oo~with~~th&#-the-time-130fied--sl-Me-the most-FeGent-SUGGessfl:J1..traoef-gas*test--is-greateF-than--3-yeafS-;

(s) The-f.kst-pe-r.fer-maooe-a-f.-tfte-fJ0fiodte-m-easurement-ef--G*R pr-essure;--SpeGifisatiGn-5-*.&A-M,--shall-be-wHhirt-24menths,--plus the-1..eo.4ays-allowed-by-.SR-3;0,.2,as-measur:ed-fr-em-the-date-of the-mest-recent-s1:K:Gessf.u~-J*e55Uf&measurement-test;-0r-wtthin 18-0-00ys-tf.-Aet-13eFfoFmeG-prevtol::lsly:

(14) Spent Fuel Pool Criticality Considerations (a) Use of spent fuel pool storage cells without NETCO-SNAP-IN rack inserts shall be restricted as follows:

1) Minimum panel Boron-10 areal density of a storage cell shall be greater than or equal to 0.014 grams per square centimeter to store fuel assemblies with the maximum in-core cold k-infinity of up to 1.235 {except as noted in a.3 below for restricted cells). The minimum panel Boron-10 areal density shall be evaluated by assuming that the panel areal density was initially equal to a value of 0.0235 grams per square centimeter.

2) A storage cell shall not contain any fuel assembly if the minimum panel Boron-10 areal density of a storage cell is less than 0.014 grams per square centimeter (except as noted in a.3 below for restricted cells). The minimum panel Boron-10 areal density shall be evaluated by assuming that the panel areal density was initially equal to a value of 0.0235 grams per square centimeter.

Renewed License No. DPR-56 Revised by letter dated August 9, 2007 Amendment No. 290 Page 7a

Design Features 4.0 Figure 4.1-1 (page 1 of 1)

Site and Exclusion Area Boundaries PBAPS UNIT 3 4.0-3 Amendment No.

Reporting Requirements 5.6 5.b Rep u r' t i n 1J I; e q u i r cm en t ~; ( con t i nu e cJ )

5.6.5

a. Core operating limits shall be established prior to each rel1Jdd cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

1. The Average Planar Linear Heat Generation Rate for Specification 3.2.1;

2. The Minimum Critical Power Ratio for Specifications 3.2.2 and 3.3.2.l;

3. The Linear Heat Generation Rate for Specification 3.2.3;

4. The Control Rod Block Instrumentation for Specification 3.3.2.1; and

5. The Oscillation Power Range Monitor COPRM)

Instrumentation for Specification 3.3.1.1.

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

1. NEDE-24011-P-A, "General Electric Standard Application for Reactor Fuel" (latest approved version as specified in the COLR)* ,.., n

'~

• 2-: Nf-OC- ~-Hi2P  ;--*!.!.Maxi*mt1m EX:t-eftded--l:-e-a*d

• 1::-i-A-e-* L+m-i-t-*a+t-d-ART&

lmf3-F-e-11em-e-At-Pr*o-grarn---Aft-a+yses--4-ef'--P-e-a-e-h--~-~-&

Powe-r---*&-t-a-t-i-e*A-*1:1-l'l-tts-2:-*-a-tTd-3,.-!!--Re-v+*s-4-efl--2,-/4a-r-efl-;--l~

3-:- .P..E-87-***FM-&---li-OG-+/--A,~tl:t-s-t-a4;t--+At*rma-t-Hy*d**r-cH:Xi**i***e A-rt-a+;Y-5-i-s--e+-P-ea-efl-Bo-t-t-effl--*004+5--2--a-RB:--3-tts-Ht-g-t-fre--F-I-BW-R GB-m*p-u-t--f'--*Co*d~;-

4-;- P+C-e-FM-&--wtt2--*A-,-"Metf:re4*-f-o-f'--&a+etti-a-t+n*g Tr a n*s-4-efrt-f-r-:i t-t-c-a-1-P-o-vre-r--R-a-t+e-s- f-of'*-&oi-+=i-*!9-§-Wa-t--e-r-Rea-et-or-s*

-E-R:-ETRA-N---TCPP.ftre} ;*

&.- P.f:-£**0***-FM-&-G&G-3--A,--!'-&.:t;-e-a-0-y-&t-at*e-FHet---P--rf&P*maft-e-Me-t-ft-od*s*

R-ep-0-r*t;-!!-;-

&-;- *P.f.&o--FM-S--GGG-4--A--,'!-f>4e-t-h-od-s-fiH0--fl.-rform-i-frt;J-B~y-s-t~

T-r-artS-4-e-A-t-AHa+:Y-S-*i*s~

continued PBAPS UN IT 3 5.0-21 Amendment No. 254

Reportin<J Requirement~;

5 . (j 5.6 Reporting Requirements 5.6.5 ~ORE OPERATING LIMITS REPORT CCOLRl (continued)

.J--*,- f18:-B--FM-&--El005-A-,-.!:-M-e-t-fto45---f-&*-P-e-r-f-er-mi+ig--BW..R--S-tetttly--

S-t--a.f.*e--Rea--t-&P--Pf\*y-s-i--s---A+i-a+y-s-4-*s-~!.-;--

&-.- *P.ft-e--fM-&*--00&6--A,--!-'-Me-t-fl-OOs-fer-Pe*r*forrni-ft§*--&WH---He+etttl

• S#e-t--y-E-v*a-Hti.Ft-i-e-A-&..!.!..-;--a-A4 9--; N-E-B0-*-3--2-4&&-*A,-*-'-~e-a-e-t-&11--~tu-&i-1+t-y--.JJ.e.-te--t--*afl-El--Su-p-p-r--e-s-s-

-5e+tt-t-i-e*A*s-!:::-'i-e-e-A-S-4ttg--&a-s-i-s--*Me-f.-A-ede+-e-g-y--A-ne-Rei--0-a-El-App-i-i--e-a-=He-11-5-;-.!.!....-Acrgtt&-t--i.-9*9-&-.-

c. The core operating 1 imits shal 1 be determined such that al 1 applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SOM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR, including any midcycle rev1s1ons or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.6.6 Post Accident Monitoring (PAM) Instrumentation Report When a report is required by Condition B or F of LCO 3.3.3.1, "Post Accident Monitoring (PAM) Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

5.6.7 Reactor Coolant Svstem (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT

( PTLR)

a. RCS pressure and temperature limits for heatup, cooldown, low temperature operation, criticality, and hydrostatic testing as well as heatup and cooldown rates shall be established and documented in the PTLR for the following:

i) Limiting Conditions for Operation Section 3.4.9, "RCS Pressure and Temperature (P/T) Limits" ii) Surveillance Requirements Section 3.4.9, "RCS Pressure and Temperature (PIT) Limits" PBAPS UN IT 3 5.0-22 Amendment No. 289