ML090440307

Correction to Pages Issues with Amendment Nos. 208, 209, and 210

ML090440307
Person / Time
Site:	Columbia
Issue date:	02/13/2009
From:	Lyon C Plant Licensing Branch IV
To:	Parrish J Entergy Northwest
Lyon, C F, NRR/DLPM, 415-2296
References
TAC MD6176, TAC MD6208, TAC MD8687
Download: ML090440307 (28)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 February 13, 2009 Mr. J. V. Parrish Chief Executive Officer Energy Northwest P.O. Box 968 (Mail Drop 1023)

Richland, WA 99352-0968

SUBJECT:

COLUMBIA GENERATING STATION - CORRECTION TO PAGES ISSUED WITH AMENDMENT NOS. 208, 209, AND 210 (TAC NOS. MD6208, MD8687, AND MD6176)

Dear Mr. Parrish:

On September 15, 16, and 30, 2008, the Nuclear Regulatory Commission (NRC) staff issued Amendment Nos. 208, 209, and 210, respectively, to Facility Operating License No. NPF-21 for Columbia Generating Station.

An administrative error was discovered in the electronic version of the amended license and technical specification pages in the Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML081900598, ML082380018, and ML082610056, for Amendment Nos. 208, 209, and 210, respectively. The error resulted in the omission of amendment numbers at the bottom of each page. In addition, TS page 3.6.4.2-3 for Amendment No. 208 was missing an amendment number on the paper copy issued on September 15, 2008.

We have enclosed copies of the corrected license and technical specification pages for these amendments. If you have questions, please contact me at me at 301-415-2296.

Sincerely, Carl F. Lyon, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-397

Enclosure:

As stated cc w/encl: Distribution via Listserv

ENCLOSURE Attachment to License Amendment No. 208, Issued September 15, 2008 Attachment to License Amendment No. 209, Issued September 16, 2008 Attachment to License Amendment No. 210, Issued September 30,2008

ATTACHMENT TO LICENSE AMENDMENT NO. 208 FACILITY OPERATING LICENSE NO. NPF-21 DOCKET NO. 50-397 Replace the following pages of the Facility Operating License No. NPF-21 and Appendix A, Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Facility Operating License REMOVE INSERT

-3 Technical Specification REMOVE INSERT 3.3.3.1-4 3.3.3.1-4 3.3.6.1-1 3.3.6.1-1 3.3.6.1-8 3.3.6.1-8 3.6.1.3-1 3.6.1.3-1 3.6.1.3-2 3.6.1.3-2 3.6.1.3-3 3.6.1.3-3 3.6.1.3-4 3.6.1.3-4 3.6.1.3-5 3.6.1.3-5 3.6.1.3-6 3.6.1.3-6 3.6.1.3-7 3.6.1.3-7 3.6.1.3-8 3.6.1.3-8 3.6.1.3-9 3.6.1.3-9 3.6.1.3-10 3.6.4.2-2 3.6.4.2-2 3.6.4.2-3 3.6.4.2-3 3.6.4.2-4

-3 (3) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source of special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

(6) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to store byproduct, source and special nuclear materials not intended for use at Columbia Generating Station. The materials shall be no more than 9 sealed neutron radiation sources designed for insertion into pressurized water reactors and no more than 40 sealed beta radiation sources designed for use in area radiation monitors. The total inventory shall not exceed 24 microcuries of strontium-90, 20 microcuries of uranium-235, 30 curies of plutonium-238, and 3 curies of americium-241.

C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of full power (3486 megawatts thermal). Items in Attachment 1 shall be completed as specified. Attachment 1 is hereby incorporated into this license.

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.2 a 8 and the Environmental Protection Plan contained in Appendix S, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

a. For Surveillance Requirements (SRs) not previously performed by existing SRs or other plant tests, the requirement will be considered met on the implementation date and the next required test will be at the interval specified in the Technical Specifications as revised in Amendment No. 149.

Amendment No.2 a 8

PAM Instrumentation 3.3.3. 1 Table 3.3.3.1-] (page 1 of ])

Post Accident Monitoring Instrumentation UHWiTIONS REFERENCED REOUIRED FRIiM REQUIRED FUNCTION  ::HAN~ELS ACTrON D.]

I. Reactor Vessel Pressure 2 Z. Reactor Vessel Water level

a. -150 inches to .. 60 inches 2 E

b. -310 inches to -]10 :nches 2

3. Suppresslon Pool Water Level

a. -25 inches to +25 inches 2

b. 2 ft to 52 ft 2

~. Suppression Chamber Pressure 2

5. Drywell Pressure

a. -5 psig to +3 psig 2

b. 0 psig to 25 pSlg 2

• . 0 psig to ]80 psig  ? E

6. PrimMY Containment Area Rad'ation 2

7. Penetration Flow Path PCIV POSltion 2 per penetration flow path (a)(bJ B. Deleted

9. Deleted

]0. EeeS Pump Room Flood Level 5 (a) Not required for isolation valves whose associated penetrat'on flew path is isolated by a~ least one closed and de-activated automatic valve. closed manual valve. blind flange. or cheCk valve wlth flow through the valve secured.

(bl Only one position indication channel is required for penetration flow paths with only one installed control room indication channel.

Columbia Ge~erating Statinn 3.3.3.1'4 Amendment No. 149,169.189,208

Primary Containment Isolation Instrumentation 3.3.6.1 3.3 INSTRUMENTATION 3.3.6.1 Primary Containment IsolaLion Instrumentation LCO 3.3.6.1 The primary containment isolation instrumentation for each Function in Table 3.3.6.1-1 shall be OPERABLE.

APPLICABILlTY: According to Table 3.3.6.1-1.

ACTIONS

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - -NOTES- - - - - - - - - -- -

1. Penetration flow paths may be unisolated intermittently under administrative controls.

2. Separate Condition entry is allowed for each channel.

COND IT ION REOUIRED ACT ION COMPLETION T1 ME A. One or more required A.l Place channel in ] 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br /> for channels inoperable. t r' i p . Functions 2. a .

2.c, 5.d, 6.a and 6.b AND 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> for Functions other than Functions 2. a, Z.c. 5. d , 6.a and 6.b R. One or more automatic B. 1 Restore isolation 1 hour Functions with crJpability, isolation capability not maintained.

(continued)

Columbia GeneraLing Station 3.3.6.1-1 Amendment No. 149.169,208

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1'1 (page 4 of 4)

Primary Containment Isolation Instrumentation APPLICABLe CO~W IT ION 5 I~O{)F S OR REOUIRED REFERENCED OTHER CHANNEtS FROM SPE':IFJED peR TRIP REQUIRED SuRVE I LLAileF ALlOWA8lE FUNrT 10'~ CO NO IT IONS SYSTH~ ACT I ON C.l RfClUIREMENTS VALUe

s. RHP SDC System Isolation

o. Pump Room Area J per room SR 3 .J. 6.1. :1 S- ISIl"F Temp~rature'- High SR 3.3.6. I .4 SR 3. J. 6. I .6

b. Pump Room Area 3 1 per room SR 3.3.6.1.3 .s. 70"F Vent i Jat ion SR 3.3.6.1.4 Di fferential SR 3.3.6.1.6 Temperature - High

c. Heat Exchanger 3 1 per room SR 3.3.6.1.3 Area SR 3.3.6.1.4 Temperature - High SR 3.3.6.1.6 Room 505 Area .s. 140"F Room 507 A"ea .s. 160°F Room tiOS Area < 150°F Roo~' 606 Area .s. 140" F 2 (d)

d. Reactor Vessel 3.4.5 .J SR 3.3.6.1.1 .? 9.5 inch~s Water Level - Low. SR 3.3.6.1.2 Level 3 SR 3.3.6.1.4 SR 3.3.fi.1.6

e. Reactor Vessel 1, 2,3 SR 3.3.6,1.2 .s. 135 psig Pressure - High SR 3.3.6.1.4 SR 3.3.6.1.6

f. Manual In it i at. ion 1 .2.3 G SR 3.3.6.1.6 NA

6. Traversing J n'.:o re Probe IsolaLlon

a. Reactor Vessel 1 .2,3 G SR 3,3.6.1.1 .? 58 inches Water Level Low SR 3.3.6. 1.2 Low. Level 2 SR 3.3.6. 1.4 SR 3.3.6.1.6

b. Drywell Pressure 1 ,2,3 G SR 3.3.6.1. I .s. 1. BB psig High SR 3.3.6. I ,2 SR 3.3.6.1.4 SR 3.3.6. J .6 rO) Only one trip syst.em required ln MDDES 4 and 5 with RHR Shutdown Coollng System integrity maintained.

Columbia Generating Station 3.3.6.] 8 Amendment No. 149,16],159,208

PC1Vs J .6. ] . J 3.6 CONTAINMENT SYSTEMS 3.6.1.3 Primary Containment Isolation Valves (PCIVs)

LCD 3.6.1.3 Each PCIV. except reactor building~tosuppression chamber vacuum breukers. shall be OPERABLE.

APPLlCAHILITY: r>10DES 1.2. and 3, When associated instrumentation is required to be OPERABLE per LCO 3.3.6.1. *Primary Containment Isolation Instrumentation.*

Acr IONS

.~ NOTES~- ~~~-~~~~~

]. Penetration flow paths may be unisolaLed intermittently under administrative controls.

2. Separate Condition entry is allowed for each penetration flow path.

3. Enter applicable Conditions and Required Actions for systems made inoperable by PCiVs.

4. Enter applicable Conditions and Required Actions of LCO 3.6.1.1. *Primary Containment." when PCIV leakage results in exceeding overal I containment leakage rate acceptance criteria.

COND] liON REQUIRED ACTION COMPLETION TIME A, - -NOTE- A.l Isolate the affected 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> except Only applicable to penetration flow path for main steam penetration flow paths by use of at least 1 i ne with two PCIVs. one closed ilnd de~activated automatic valve, One or more closed manual valve, 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br /> for' penetration flow paths tl1ind flange. or main steam line with one PCIV check valve with flow inoper'able for reasons through the valve other than secured.

Condition D.

(continuPd)

Columbia Generating Station 3.6.1.3-1 Amendment No. H9 .169 208 1

pcrvs 3.6. 1 . l ACIIONS CONDITION REQUIRED ACTION CO~1 PLI:.T rON TIM E A. (continued) A.2 - - - - - - - - NOTE S- - - - -

1. Isolation devices in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked.

sealed, or otherwise secured may be verified by use of administrative means.

Verify the affected Once per penetration flow path 31 days for is isolated. isolation devices outside primary containment Prior to entering MODE 2 or ] from MODE 4 if primary containment was de-inerted while in MODE 4, if not performed within the previous 92 days. for isoidtion devices inside primary containment (continued)

Columbia Generating Station 3.6.1.]-2 Amendment No. +4-9--;r-&9 ,208

pcrvs 3.6.1 .3 ACTIONS COND IT ION REOIJ I RED AU j ON COMPLETfON TIME B. .. ---- NOTE--- B. 1 Isola t e tile a i f ected 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Only applicable to penetration flow path penetration flow paths by use of at least with two PCIVs. one closed and de-activated automatic valve.

One or more closed manual valve, penetration flow paths or b'lind flange.

with two PCIVs inoperable for reasons other than Condition D.

C. ---------NOTE--- .... C. 1 IsolaLe the affected 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> except Only applicable to penetration flow path for excess flow penetration flow paths by use of at least clleck va 1ves with only one PCIV. one closed and (UCVs) de activated automatic valve, One or more closed manual valve, penetration flow paths or blind flange. 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> for with one PCIV EFCVs inoperable for reasons other than Condition D.

(continued)

Columbia Generating Station 3.6.1.33 L\rnenU!llent No. 149.169,208

PCIVs 3.6.1.3 ACTIONS CONDITION REOliIRFD ACTION COMPLET rON TIMF C. (continued) C.2 -NOTES"--'-'

1. Isolation devices in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked.

sealed. or otherwise secured may be verified by use of administrative means.

Verify the affected Once per penetration flow path 31 days for is isolated. isolation devices outside primary containment fJrior to entering MODE 2 or 3 from MODE 4 it pt"imary containment was de inerted while in MODE 4. if not performed within the previous 92 days, for isolation devices inside primary containment (continued)

Columbia Generating Station 3. fj . 1 .3 - 4 Amendment No. 149.]69,208

PC[Vs 3.6.1 .]

ACT IONS CONOITION r~EOU I RED ACT l UN COMPLETION TIME

n. One or more secondary D. 1 Restore leakage rate 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> for containment bypass to within limit. hydrostatically leakage rate, MSIV tested 1ine leakage rate. or leakage not on hydrostatically tested a closed system lines leakage rate not within limit.

4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />'s for secondary containment bypcss ieakage 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br /> for MSIV leakage 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> for' hydrostatically tested 1i ne leakage on a closed system E. Required Action and E. 1 Be in MODE 3. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> associated Completion Time of Condition A, AND B. C, or 0 not met in MODE 1. 2, or 3. E.2 Be in MODE 4. ]6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> (continued)

Columbia Generating Station ],6.1.3 5 Amendment No. 149,1',9,208

PCIVs 3.6.1.3 ACTIONS CONDITlON RrOlJ I .';:[0 ,\C TI ON Cor>1PI ETlaN TIME F. Required Action and F.1 Initiate action to Immediately associated Completion suspend operations rime of Condition A, with a potential for S, C, or D not met for draining the reactor PCIV(s) required to be vessel (OPDRVs).

OPERABLE during MODE 4 or 5. OR F.2 Initiate action to Immediately restore valve(s) to OPERABLE status.

I Columbia Generating Station 3.6.1.3-6 Amendment No. 149.169,208

PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.0.1.3.: ----NOTE ----------

Not required to be met when the 24 inch and 30 inch primary containment purge valves are open for inerting, de-inerting, pressure control, ALARA or air quality considerations for personnel entry, or Surveillances that require the valves to be open.

Verify each 24 inch and 30 inch primary 31 days containment purge valve is closed.

SR 3.6.1.3.2 ------ --- -----NOTES----*_---*-- -<--

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Not required to be met for PCIVs that are open under administrative controls.

Verify each primary containment isolation 31 days manual valve and blind flange that is located outside primary containment and not locked, sealed, or otherwise secured and is required to be closed during accident conditions is closed.

(continued)

Columbia Generating Station 3.6.1.3-7 Amendment No. 149,169,208

PCIVs 3.6. 1 .3 SURVEILlANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.3.3 - - -- - - - - - - - - - - - - -NOTES- - - _.. - - - - - - - - . -

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Not required to be met for PCIVs that are open under administrative controls.

Verify each primary containment isolation Pr'ior to manual valve and blind flange that is entering MODE 2 located inside primary containment and or 3 from not locked. scaled. or otherwise secured MODE 4 if and is required to be closed during primary accident conditions is closed. containmpnt was de' i nerted while in MODE 4. if not performed within the previous 92 days SR 3.6.1.3.4 Verify continuity of the traversing 31 days incore probe (TIP) shear isolation valve explosive charge.

SR 3.6.1.3.5 Verify the isolation time of each power In accordance operated. automatic PCIV. except MSIVs. wi th Lhe is-within limits. Inservice Testing Program (continued)

Columbia Generating Station 3.6.1.3-8 Amendment No.

149.169.170.175,199 208f

PCIVs 3.6.1 .3 SURVEILlANCl ~EOUIREMENrs SURVEILLANCl FREOUENCY SR 3.0.1.3.6 Verify the isolation time of each MSIV is In accordance 2 3 seconds and ~ 5 seconds. with the Jnservice Testing Program SR 3.6.1.3.7 Verify each automatic PCIV actuates to 24 months the isolation position on an actual or simulated isolation signal.

SR 3.6.1.3.8 Verify a representative sample of reactor 24 months instrument 1 ine [FCVs actuate to the isolation position on an actual or simulated instrument line break signal.

SR 3.6.1.3.9 Remove and test the explosive squib from 24 months on a each shear isolation valve of the TIP STAGGERED TEST System. BASIS SR 3.6.1.3.10 Verify the combined leakage rate for all In accordance secondary containment bypass leakage with the paths is .s. 0.04% primary containment Primary volume/day when pressurized to ~ Pd' Containment Leakage Rate resting Program (continued)

Colu~bia Generating Station 3.6.1.3-9 Amendment No. 149,169199

PCIVs 3.6.1 .3 SURVEILLANCE REQUIREMENTS SliRVEI LlANCE FREQUENCY SR 3.6.1.3.11 Verify leakage rate through each MSIV is In accordance

~ 16.0 scfh when tested at 2 25.0 psig. with the Primary Containment Leakage Rate Test.inC) Program SR 3.6.1.3.12 Verify combined leakage rate through In accordance hydrostatically tested lines that with the penetrate the primary containment. is Primary within limits. Containment.

Leakage Rate Testing Program lumbia Generating St.ation 3.6.1.3 10 Amecdm,'nt NO.20~

..,C I Vs

~ . h . ,1 . ?

\('FlnNS CO~W!FION RFJUIRFD ACT[Ii~J COMPurlON 1 1M E A (continued) A7., . - NO TE S

1. [sol d t i 011 devices ill ~l i 9 rl radiation a r'ea S may be verified by use of administrative mr.ans.

2. [solation devices that are locked, sealed, or oUlerwise secured may be verified by use of administrative means.

---

~-_._---~-~. - -

Verify ttle affected Once per 31 days penetration fl ow path is isolated.

B. - . - NOTE - - - - - - B. 1 Isolat.e the affected 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> Only applicable to penetration FJow path penetration flow paths by use of at least wi t h two isolation one closed and valves. de-activated

- -- - - -- - - - -- - . -- - - - - - aut.omatic valve.

closed manual valve.

One or more or blind Flange.

penetration flow pat.hs with two SCIVs inoperable.

(cant i nued)

Columbia Cenpratilllj Station ),6.4.2 2 ArnencJrnent NO. 149,169,199,208

'-,C I Vc,

~ . () . :1 . ?

\" r [ IlNS CONDlrrON krUIlIRED I'lL r I() N COMPU TION riME

c. Re q II i I P l: t, c t i iJ Il llil (j C.l B(, ill MOU[ \. 12 flO 1I rS ds<,ociatf'd Complr:'tion rime of COllclitioll A AND or B not met i rl MOUE l. 2. or 3. C.? Be ill MODE 4. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> D. Required Action and 0.1 Initiate action Immediately 11ssoci ated Completion to suspend Time of Condition A OPDRVs.

or" B not. met. during OPDRVs.

CQllllnlJia Cf:?IIPrating '-,tatioli 3.6.4.2 3 ,\rnenrJmen t No. 149. 169.J...l,1..9 nf'i

SCIVs 3.6.4.2 SURVEILLANCE REQUIREMENTS SURVE [LLf\NCF SR 3.6.4.2.1 NorES*

1. Val vf? san (j t) 1i nd f 1drl 9e sin ~) i Cd ~l r' ad i a t ion a r P r1 sma y be ve r i fie c1 by use () f r1 d mi il i s t ,'d t i V l' con t (' 0 Is.

2. Not rcquir'.,<J 1.0 be llIet FlH' SCIVs that are open 1I1llj e r 'H1rni II i s t r' a t j ve controls.

Verify each secondary containment 31 clays isolation manual valve and blind flange that is not locked, sealed, or otherwise secured, and is required to be closed during accident conditions is closed.

SR 3.6.4.2.2 Verify the isolation time of each power In accordance operated. automatic SCIV is within with the 1 i mi t s . fnservice Testing Program SR 3.6.4.2.3 Verify each dutomatic SCIV actuates to 24 rnonU1S thr isolation position on an actual Ot' simulated automatic isolation signal.

C'J 1 II mb i rJ r, P Ii e r d t. j II 9 S t d til) II

ATTACHMENT TO LICENSE AMENDMENT NO. 209 FACILITY OPERATING LICENSE NO. NPF-21 DOCKET NO. 50-397 Replace the following pages of the Facility Operating License No. NPF-21 and Appendix A, Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Facility Operating License REMOVE INSERT

-3 Technical Specification REMOVE INSERT 3.10.1-1 3.10.1-1

-3 (3) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source of special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

(6) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to store byproduct, source and special nuclear materials not intended for use at Columbia Generating Station. The materials shall be no more than 9 sealed neutron radiation sources designed for insertion into pressurized water reactors and no more than 40 sealed beta radiation sources designed for use in area radiation monitors. The total inventory shall not exceed 24 microcuries of strontium-90, 20 microcuries of uranium-235, 30 curies of plutonium-238, and 3 curies of americium-241.

C. This license 'shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of full power (3486 megawatts thermal). Items in Attachment 1 shall be completed as specified. Attachment 1 is hereby incorporated into this license.

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment NO.2 0 9 and the Environmental Protection Plan contained in Appendix S, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

a. For Surveillance Requirements (SRs) not previously performed by existing SRs or other plant tests, the requirement will be considered met on the implementation date and the next required test will be at the interval specified in the Technical Specifications as revised in Amendment No. 149.

Amendment No. 209

Inservice Leak and Hydrostatic Testing Operation 3.10.1 3.10 SPECIAL OPERATIONS 3.10.1 Inservice Leak and Hydrostatic Testi~g Operation LCD 3.10.1 The average reactor coolant temperature specified in Table 1.1-1 for MODE 4 may be changed to "NA." and operation considered not to be in MODE 3; and the requirements of LCO 3.4.10, "Residual Heat Removal (RHR) Shutdown Cooling System-Cold Shutdown," may be suspended to allow reactor coolant temperature> 200°F:

For performance of an inservice leak or hydrostatic test, As a consequence of maintaining adequate pressure for an inservice leak or hydrostatic test, or As a consequence of maintaining adequate pressure for control rod scram time testing initiated in conjunction with an inservice leak or hydrostatic test, provided the following MODE 3 LCOs are met:

a. LCD 3.3.6.2. "Secondary Containment Isolation Instrumentation." Functions 1. 3, and 4 of Table 3.3.6.2-1;

b. LCO 3.6.4.1. "Secondary Containment";

c. LCD 3.6.4.2. "Secondary Containment Isolation Valves (SCIVs)"; and

d. LCD 3.6.4.3, "Standby Gas Treatment (SGT) System."

APPLICABI LITY: MODE 4 with average reactor coolant temperature> 200°F.

Columbia Generating Station 3.10.1-1 Amendment No. 149.169 209

ATTACHMENT TO LICENSE AMENDMENT NO.210 FACILITY OPERATING LICENSE NO. NPF-21 DOCKET NO. 50-397 Replace the following pages of the Facility Operating License No. NPF-21 and Appendix A, Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Facility Operating License REMOVE INSERT

-3 Technical Specification REMOVE INSERT 3.3.5.2-4 3.3.5.2-4 3.5.2-3 3.5.2-3

-3 (3) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30,40 and 70, to receive, possess, and use in amounts as required any byproduct, source of special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

(6) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to store byproduct, source and special nuclear materials not intended for use at Columbia Generating Station. The materials shall be no more than 9 sealed neutron radiation sources designed for insertion into pressurized water reactors and no more than 40 sealed beta radiation sources designed for use in area radiation monitors. The total inventory shall not exceed 24 microcuries of strontium-90, 20 microcuries of uranium-235, 30 curies of plutonium-238, and 3 curies of americium-241.

C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of full power (3486 megawatts thermal). Items in Attachment 1 shall be completed as specified. Attachment 1 is hereby incorporated into this license.

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 210 and the Environmental Protection Plan contained in Appendix S, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

a. For Surveillance Requirements (SRs) not previously performed by existing SRs or other plant tests, the requirement will be considered met on the implementation date and the next required test will be at the interval specified in the Technical Specifications as revised in Amendment No. 149.

Amendment No. 210

Table 3.3.5.2-1 (page 1 of 1)

React'.1r Core I'i0lati,)n Cooling System Instrulncr.tation CONDITIONS REr}U IRED REFEREnCED CHANNELS FROM PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION FUNCT 19N ACTION.A.l REQUIREMUH5 VALUE

l. Reactor Vessel Water 4 B 5R 3.3.5.2.1 > -58 inches Level - Low Low. SR 3.3.5.2.2 Level 2 SR 3.3.5.2.3 SR 3.3.5.2.4

2. Reactor Vessel Water 2 C SR 3.3.5.2.1 ~ 56 inches Level - High. Level 8 SR 3.3.5.2.2 SR 3.3.5.2.3 SR 3.3.5.2.4

3. Condensote Storage 2 D SR 3.3.5.2.1 ~ 447 ft 7 Tank Level - Low 5R 3.3.5.2.2 i I1ches SR 3.3.5.2.3 elevatiDn SR 3.3.5.2.4

4. t~anual Initiation 2 C SR 3.3.5.2.4 NA t: I) 1 1/111 b i,] Gi? ne r ,J till IJ S t r1 t i rj n AmL'willH'nt 1\10. 1'19,169,210

Eces - Shutdown 3.5.2 SURVErLLANcE REOU[REMENTS SURVEI LLANCE FREQUENCY SR 3.5.2.1 Verify, for each required low pressure ECCS 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> injection/spray subsystem, the suppression pool water level is ~ 18 ft 6 inches.

SR 3.5.2.2 Verify, for the required High Pressure Core 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> Spray (HPCS) System. the:

a. Suppression pool water level is

~ 18 ft 6 inches: or

b. Condensate storage tank (CST) water level is ~ 16.5 ft in a single {ST or

~ 10.5 ft in e~ch CST.

SR 3.5.2.3 Verify, for each required ECCS injection/ 31 dilYs spray subsystem, the piping is filled with water from the pump discharge valve to the injection valve.

SR 3.5.2.4 - - - - . - - - - . - - . - . - -NOT E - - ... - - . - - . - . - .

One low pressure coolant injection (LPCI) subsystem may be considered OPERABLE during alignment and operation for decay heat removal. if capilble of being milnually realigned and not otherwise inoperable.

Verify each required ECCS injection/spray 31 dJys subsystem manual. power operated. ilnd automiltic valve in the flow path, that is not locked, seJled, or otherwise secured in position, is in the correct position.

(continued)

ColumbiJ GenerJting Station 1.5.2-3 Amendment No.

1'19.150.165.169,210

ML090440307 OFFICE NRRlLPL4/PM NRRlLPL4/LA NRR/LPL4/BC NRRlLPL4/PM NAME FLyon JBurkhardt MMarkley BSingal for FLyon DATE 2/13/09 2/13/09 2/13/09 2/13/09