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
SURVEILLANCE REQUIREMENTS
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
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 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
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
3.10.1-1 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 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.
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- -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
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
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