united states nuclear regulatory commission … · february 13, 2009 . mr. j. v. parrish chief...

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 ML08261 0056, 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- -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 a8 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 a8

PAM Instrumentation 3.3.3. 1

Post Table 3.3.3.1-] (page 1 of ])

Accident Monitoring Instrumentation

FUNCTION REOUIRED ::HAN~ELS

UHWiTIONS REFERENCED

FRIiM REQUIRED ACTrON D.]

I.

Z.

Reactor Vessel Pressure

Reactor Vessel Water level

2

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

3.

b. -310 inches to -]10 :nches

Suppresslon Pool Water Level

2

a. -25 inches to +25 inches 2

~.

5.

b. 2 ft to 52 ft

Suppression Chamber Pressure

Drywell Pressure

a. -5 psig to +3 psig

2

2

2

b. 0 psig to 25 pSlg 2

6.

7.

B.

9.

]0.

•. 0 psig to ]80 psig

PrimMY Containment Area Rad'ation

Penetration Flow Path PCIV POSltion

Deleted

Deleted

EeeS Pump Room Flood Level

2 per flow

?

2

penetration path (a)(bJ

5

E

(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 channels inoperable.

A.l Place channel in t r' i p .

] 2 hours for Functions 2. a . 2.c, 5.d, 6.a and 6.b

AND

24 hours for Functions other than Functions 2. a, Z.c. 5. d , 6.a and 6.b

R. One or more automatic Functions with isolation capability not maintained.

B. 1 Restore isolation crJpability,

1 hour

(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

FUNrT 10'~

APPLICABLe I~O{)F S OR

OTHER SPE':IFJED

CO NO IT IONS

REOUIRED CHANNEtS peR TRIP SYSTH~

CO~W IT ION 5 REFERENCED

FROM REQUIRED

ACT I ON C.l SuRVE I LLAileF RfClUIREMENTS

ALlOWA8lE VALUe

s. RHP SDC System Isolation

o. Pump Room Area Temp~rature'-High

J per room SR SR SR

3 .J. 6.1. :1 3.3.6. I .4 3. J. 6. I .6

S- ISIl"F

b. Pump Room Area Vent i Jat ion Di fferential Temperature - High

3 1 per room SR SR SR

3.3.6.1.3 3.3.6.1.4 3.3.6.1.6

.s. 70"F

c. Heat Exchanger Area Temperature - High

3 1 per room SR SR SR

3.3.6.1.3 3.3.6.1.4 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

d. Reactor Vessel Water Level - Low. Level 3

3.4.5 2(d) .J SR SR SR SR

3.3.6.1.1 3.3.6.1.2 3.3.6.1.4 3.3.fi.1.6

.? 9.5 inch~s

e. Reactor Vessel Pressure - High

1 , 2 , 3 SR SR SR

3.3.6,1.2 3.3.6.1.4 3.3.6.1.6

.s. 135 psig

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 Water Level Low Low. Level 2

1 .2,3 G SR SR SR SR

3,3.6.1.1 3.3.6. 1.2 3.3.6. 1.4 3.3.6.1.6

.? 58 inches

b. Drywell High

Pressure 1 ,2,3 G SR SR SR SR

3.3.6.1. I 3.3.6. I ,2 3.3.6.1.4 3.3.6. J .6

.s. 1. BB psig

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-Only applicable to penetration flow paths with two PCIVs.

One or more penetration flow paths with one PCIV inoper'able for reasons other than Condition D.

A.l Isolate the affected penetration flow path by use of at least one closed ilnd de~activated

automatic valve, closed manual valve, tl1ind flange. or check valve with flow through the valve secured.

4 hours except for main steam 1i ne

8 hours for' main steam line

(continuPd)

Columbia Generating Station 3.6.1.3-1 Amendment No. H9 .169 2081

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---Only applicable to penetration flow paths with two PCIVs.

One or more penetration flow paths with two PCIVs inoperable for reasons other than Condition D.

B. 1 Isola t e tile aifected penetration flow path by use of at least one closed and de-activated automatic valve. closed manual valve, or b'lind flange.

1 hour

C. ---------NOTE--- .... Only applicable to penetration flow paths with only one PCIV.

One or more penetration flow paths with one PCIV inoperable for reasons other than Condition D.

C. 1 IsolaLe the affected penetration flow path by use of at least one closed and de activated automatic valve, closed manual valve, or blind flange.

4 hours except for excess flow clleck va 1ves (UCVs)

72 hours for EFCVs

(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 containment bypass leakage rate, MSIV leakage rate. or hydrostatically tested lines leakage rate not within limit.

D. 1 Restore leakage rate to within limit.

4 hours for hydrostatically tested 1ine leakage not on a closed system

4 hour's for secondary containment bypcss ieakage

8 hours for MSIV leakage

72 hours for' hydrostatically tested 1i ne leakage on a closed system

E. Required Action and associated Completion Time of Condition A, B. C, or 0 not met in

E. 1

AND

Be in MODE 3. 12 hours

MODE 1. 2, or 3. E.2 Be in MODE 4. ]6 hours

(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 associated Completion rime of Condition A, S, C, or D not met for PCIV(s) required to be OPERABLE during MODE 4 or 5. OR

F.2

I

Initiate action to suspend operations with a potential for draining the reactor vessel (OPDRVs).

Initiate action to restore valve(s) to OPERABLE status.

Immediately

Immediately

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 containment purge valve is closed.

31 days

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 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.

31 days

(continued)

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

PCIVs 3.6. 1 .3

SURVEILlANCE REQUIREMENTS

SR 3.6.1.3.3

SURVEILLANCE

- - -- - - - - - - - - - - - - -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 manual valve and blind flange that is located inside primary containment and not locked. scaled. or otherwise secured and is required to be closed during accident conditions is closed.

FREQUENCY

Pr'ior to entering MODE 2 or 3 from MODE 4 if primary 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 incore probe (TIP) shear explosive charge.

traversing isolation valve

31 days

SR 3.6.1.3.5 Verify the isolation time operated. automatic PCIV. is-within limits.

of each power except MSIVs.

In accordance wi th Lhe Inservice Testing Program

(continued)

Columbia Generating Station 3.6.1.3-8 Amendment No. 149.169.170.175,199 f 208

PCIVs 3.6.1 .3

SURVEILlANCl ~EOUIREMENrs

SR 3.0.1.3.6

SURVEILLANCl

Verify the isolation time of each 2 3 seconds and ~ 5 seconds.

MSIV is

FREOUENCY

In accordance with the Jnservice Testing Program

SR 3.6.1.3.7 Verify each automatic PCIV actuates the isolation position on an actual simulated isolation signal.

to or

24 months

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

24 months

SR 3.6.1.3.9 Remove and each shear System.

test the explosive squib from isolation valve of the TIP

24 months STAGGERED BASIS

on a TEST

SR 3.6.1.3.10 Verify the combined leakage rate for secondary containment bypass leakage paths is .s. 0.04% primary containment volume/day when pressurized to ~ Pd'

all In accordance with the Primary Containment Leakage Rate resting Program

(continued)

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

PCIVs 3.6.1 .3


SliRVEI LlANCE FREQUENCY

SR 3.6.1.3.11 Verify leakage rate through each MSIV is ~ 16.0 scfh when tested at 2 25.0 psig.

In accordance with the Primary Containment Leakage Rate Test.inC) Program

SR 3.6.1.3.12 Verify combined leakage rate through hydrostatically tested lines that penetrate the primary containment. is within limits.

In accordance with the Primary Containment. Leakage Rate Testing Program

lumbia Generating St.ation 3.6.1.3 10 Amecdm,'nt NO.20~

\('FlnNS

CO~W!FION

A (continued)

B. - . - NOTE - - - - - - Only applicable to penetration flow pathswi t h two isolation valves. - -- - - - - - - - -- - . - - - - - - -

One or more penetration flow pat.hswith two SCIVs inoperable.

RFJUIRFD ACT[Ii~J

. - A7., NO TE S 1. [sol d t i 011 devices

ill ~l i 9 rl radiation ar'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 penetration fl ow pathis isolated.

B. 1 Isolat.e the affected penetration FJow pathby use of at least one closed and de-activated aut.omatic valve. closed manual valve. or blind Flange.

..,C I Vs ~ . h . ,1 . ?

COMPurlON 1 1M E

Once per 31 days

4 hours

(cant i nued)

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

;\" r [ IlNS

CONDlrrON

c. ReqII i I P l: t, c t i iJ Il llil (j

ds<,ociatf'd Complr:'tionrime of COllclitioll A or B not met i rl MOUE l. 2. or 3.

D. Required Action and 11ssoci ated CompletionTime of Condition A or" B not. met. during OPDRVs.

krUIlIRED I'lL r I() N

C.l

AND

C.?

B(,

Be

ill

ill

MOU[

MODE

\.

4.

0.1 Initiate action to suspendOPDRVs.

'-,C I Vc, ~ . () . :1 . ?

COMPU TION riME

12 flO 1I r S

36 hours

Immediately

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


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 dmi 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 er 'H1rni II i s t r' a t j ve controls.

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

31 clays

SR 3.6.4.2.2 Verify the isolation time of each poweroperated. automatic SCIV is within 1 i mi t s .

In accordance with the fnservice Testing Program

SR 3.6.4.2.3 Verify each dutomatic SCIV actuates to thr isolation position on an actual Ot' simulated automatic isolation signal.

24 rnonU1S

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

ATTACHMENT TO LICENSE AMENDMENT NO. 209


DOCKET NO. 50-397



REMOVE INSERT

-3- -3


REMOVE INSERT

3.10.1-1 3.10.1-1

- 3


(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



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:




The Technical Specifications contained in Appendix A, as revised through Amendment NO.2 09 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.


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


DOCKET NO. 50-397



REMOVE INSERT

-3- -3


REMOVE INSERT

3.3.5.2-4 3.3.5.2-4 3.5.2-3 3.5.2-3

- 3


(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



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:




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.


Amendment No. 210

Table 3.3.5.2-1 (page 1 of 1)

React'.1r Core I'i0lati,)n Cooling System Instrulncr.tation

FUNCTION

REr}U IRED CHANNELS

PER FUNCT 19N

CONDITIONS REFEREnCED

FROM REQUIRED

ACTION.A.l SURVEILLANCE REQUIREMUH5

ALLOWABLE VALUE

l. Reactor Vessel Water Level - Low Low. Level 2

4 B 5R SR SR SR

3.3.5.2.1 3.3.5.2.2 3.3.5.2.3 3.3.5.2.4

> -58 inches

2. Reactor Vessel Water Level - High. Level 8

2 C SR SR SR SR

3.3.5.2.1 3.3.5.2.2 3.3.5.2.3 3.3.5.2.4

~ 56 inches

3. Condensote Storage Tank Level - Low

2 D SR 5R SR SR

3.3.5.2.1 3.3.5.2.2 3.3.5.2.3 3.3.5.2.4

~ 447 ft 7 i I1ches elevatiDn

4. t~anual Initiation 2 C SR 3.3.5.2.4 NA

t: I) 11/111 b i,] Gi? ner ,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

SR 3.5.2.1

SURVEI LLANCE

Verify, for each required low pressure ECCS injection/spray subsystem, the suppression pool water level is ~ 18 ft 6 inches.

12

FREQUENCY

hours

SR 3.5.2.2 Verify, for the required High Pressure Core 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.

12 hours

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

31 dilYs

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 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.

31 dJys

(continued)

ColumbiJ GenerJting Station 1.5.2-3 Amendment No. 1'19.150.165.169,210

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, I\I1D8687, 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 ML08261 0056, 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,

IRAJ

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

DISTRIBUTION: PUBLIC RidsNrrDorlLpl4 Resource RidsOgcRp Resource LPLIV Reading RidsNrrPMColumbia Resource RidsRgn4MailCenter Resource RidsAcrsAcnw_MailCTR Resource RidsNrrLA.IBurkhardt Resource

ADAMS Accession No 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

OFFICIAL RECORD COPY