ML090440307: Difference between revisions
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| number = ML090440307 | | number = ML090440307 | ||
| issue date = 02/13/2009 | | issue date = 02/13/2009 | ||
| title = | | title = Correction to Pages Issues with Amendment Nos. 208, 209, and 210 (TAC Nos. MD6208, MD8687, and MD6176) | ||
| author name = Lyon C F | | author name = Lyon C F | ||
| author affiliation = NRC/NRR/DORL/LPLIV | | author affiliation = NRC/NRR/DORL/LPLIV | ||
Line 14: | Line 14: | ||
| page count = 28 | | page count = 28 | ||
| project = TAC:MD6176, TAC:MD6208, TAC:MD8687 | | project = TAC:MD6176, TAC:MD6208, TAC:MD8687 | ||
| stage = | | stage = Acceptance Review | ||
}} | }} | ||
Line 39: | Line 39: | ||
According to Table 3.3.6.1-1. | According to Table 3.3.6.1-1. | ||
ACTIONS ------------------------------NOTES-----------Penetration flow paths may be unisolated intermittently under administrative controls. Separate Condition entry is allowed for each channel. COND IT I ON REOUIRED ACT ION COMPLETION T1 ME A. One or more required channels inoperable. | ACTIONS ------------------------------NOTES-----------Penetration flow paths may be unisolated intermittently under administrative controls. Separate Condition entry is allowed for each channel. COND IT I ON 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 | A.l Place channel in t r' i p. ] [[estimated NRC review hours::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 . 2.c, 5.d, 6.a and 6.b AND [[estimated NRC review hours::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. | : 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) | B. 1 Restore isolation crJpability, 1 hour (continued) | ||
Line 54: | Line 54: | ||
shall be r>10DES 1.2. and 3, associated instrumentation is required to be OPERABLE per LCO 3.3.6.1. *Primary Containment Isolation Instrumentation.* | shall be r>10DES 1.2. and 3, associated instrumentation is required to be OPERABLE per LCO 3.3.6.1. *Primary Containment Isolation Instrumentation.* | ||
Acr IONS Penetration flow paths may be unisolaLed intermittently under administrative controls. Separate Condition entry is allowed for each penetration flow path. Enter applicable Conditions and Required Actions for systems made inoperable by PCiVs. 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. | Acr IONS Penetration flow paths may be unisolaLed intermittently under administrative controls. Separate Condition entry is allowed for each penetration flow path. Enter applicable Conditions and Required Actions for systems made inoperable by PCiVs. 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, -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 automatic valve, closed manual valve, tl1ind flange. or check valve with flow through the valve secured. 4 hours except for main steam 1 i ne 8 hours for' main steam line (continuPd) | COND] liON REQUIRED ACTION COMPLETION TIME A, -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 automatic valve, closed manual valve, tl1ind flange. or check valve with flow through the valve secured. [[estimated NRC review hours::4 hours]] except for main steam 1 i ne [[estimated NRC review hours::8 hours]] for' main steam line (continuPd) | ||
Columbia Generating Station Amendment No. H9 .169 208 1 pcrvs 3.6. 1.l ACIIONS CONDITION REQUIRED ACTION C PL I:.T rON TIM E A. (continued) | Columbia Generating Station Amendment No. H9 .169 208 1 pcrvs 3.6. 1.l ACIIONS CONDITION REQUIRED ACTION C PL I:.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. | 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. | ||
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Columbia Generating Station 3.6.1.]-2 Amendment No. +4-9--;r-&9 | Columbia Generating Station 3.6.1.]-2 Amendment No. +4-9--;r-&9 | ||
,208 pcrvs 3.6.1 .3 ACTIONS COND IT I ON REOIJ I RED AU j ON COMPLETfON TIME B. .. 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 a ifec ted 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. | ,208 pcrvs 3.6.1 .3 ACTIONS COND IT I ON REOIJ I RED AU j ON COMPLETfON TIME B. .. 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 a ifec ted 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. | ||
.... 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 1 ves (UCVs) 72 hours for EFCVs (continued) | .... 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. [[estimated NRC review hours::4 hours]] except for excess flow clleck va 1 ves (UCVs) [[estimated NRC review hours::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 T IMF C. (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 T IMF C. (continued) | ||
C.2 -NOTES"--'-' | 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. | : 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) | 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 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 1 ine 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 3. fj . 1 .3 -4 Amendment No. 149.]69,208 PC[Vs 3.6.1 .] ACT IONS CONOITION 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. [[estimated NRC review hours::4 hours]] for hydrostatically tested 1 ine leakage not on a closed system 4 hour's for secondary containment bypcss ieakage [[estimated NRC review hours::8 hours]] for MSIV leakage [[estimated NRC review hours::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. [[estimated NRC review hours::12 hours]] MODE 1. 2, or 3. E.2 Be in MODE 4. ][[estimated NRC review hours::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). | 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.: | 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.: | ||
Line 83: | Line 83: | ||
. -A7.NO TE S [sol d t i 011 devices ill i 9 rl radiation a r'ea S may be verified by use of administrative mr.ans. [solation devices that are locked, sealed, or oUlerwise secured may be verified by use of administrative means. | . -A7.NO TE S [sol d t i 011 devices ill i 9 rl radiation a r'ea S may be verified by use of administrative mr.ans. [solation devices that are locked, sealed, or oUlerwise secured may be verified by use of administrative means. | ||
--Verify ttle affected penetration fl ow path is isolated. | --Verify ttle affected penetration fl ow path is isolated. | ||
B. Isolat.e the affected penetration FJow path by use of at least one closed and de-activated aut.omatic valve. closed manual valve. or b lind Flange. ..,C IV s . 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 | B. Isolat.e the affected penetration FJow path by use of at least one closed and de-activated aut.omatic valve. closed manual valve. or b lind Flange. ..,C IV s . h . ,1 .? COMPurlON 1 1M E Once per 31 days [[estimated NRC review hours::4 hours]] (cant i nued) Columbia Cenpratilllj Station ),6.4.2 2 ArnencJrnent NO. 149,169,199,208 | ||
;\" r [IlNS CONDlrrON R e q II i I P l: t, c t i iJ Il llil (j ds<,ociatf'd Complr:'tion rime of COllclitioll A or B not met i rl MOUE l. 2. or 3. Required Action and 11ssoci ated Completion Time 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 suspend OPDRVs. '-,C I Vc, .().:1 .? COMPU T ION riME 12 flO 1I r S 36 hours Immediately CQllllnlJia Cf:?IIPrating | ;\" r [IlNS CONDlrrON R e q II i I P l: t, c t i iJ Il llil (j ds<,ociatf'd Complr:'tion rime of COllclitioll A or B not met i rl MOUE l. 2. or 3. Required Action and 11ssoci ated Completion Time 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 suspend OPDRVs. '-,C I Vc, .().:1 .? COMPU T ION riME 12 flO 1I r S [[estimated NRC review hours::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 v f? san (j t) 1ind f 1 drl 9 e sin i Cd r' ad i a t ion a r P r1 sma y be ve r i fie c1 by use () f r1 d m i 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' at j v e controls. | '-,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 v f? san (j t) 1ind f 1 drl 9 e sin i Cd r' ad i a t ion a r P r1 sma y be ve r i fie c1 by use () f r1 d m i 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' at j v e controls. | ||
Verify each secondary containment 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. 31 clays SR 3.6.4.2.2 Verify the isolation time of each power operated. | Verify each secondary containment 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. 31 clays SR 3.6.4.2.2 Verify the isolation time of each power operated. | ||
Line 104: | Line 104: | ||
> -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 | > -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. | : 4. | ||
Initiation 2 C SR 3.3.5.2.4 NA t: I) 1 1/111 b i,] G i? 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 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 CST. 12 hours SR 3.5.2.3 Verify, for each required ECCS injection/ | Initiation 2 C SR 3.3.5.2.4 NA t: I) 1 1/111 b i,] G i? 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 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 CST. [[estimated NRC review hours::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 ----. ----. --. -. -- | 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--... --. --. -. -. | NOT E--... --. --. -. -. |
Revision as of 05:15, 17 April 2019
ML090440307 | |
Person / Time | |
---|---|
Site: | Columbia ![]() |
Issue date: | 02/13/2009 |
From: | Lyon C F Plant Licensing Branch IV |
To: | Parrish J V Entergy Northwest |
Lyon, C F, NRR/DLPM, 415-2296 | |
References | |
TAC MD6176, TAC MD6208, TAC MD8687 | |
Download: ML090440307 (28) | |
Text
UNITED NUCLEAR REGULATORY 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 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
Attachment to License Amendment No. 208, Issued September 15, Attachment to License Amendment No. 209, Issued September 16, Attachment to License Amendment No. 210, Issued September ATTACHMENT TO LICENSE AMENDMENT NO. FACILITY OPERATING LICENSE NO. DOCKET NO. 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 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
-3Pursuant 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; 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 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. 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. 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: 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. 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. 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 Post Table 3.3.3.1-] (page 1 of ]) Accident Monitoring Instrumentation FUNCTION REOUIRED 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 Not required for isolation valves whose associated penetrat'on flew path is isolated by least one closed and de-activated automatic valve. closed manual valve. blind flange. or cheCk valve wlth flow through the valve secured. Only one position indication channel is required for penetration flow paths with only one installed control room indication channel. Columbia 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 Containment IsolaLion Instrumentation LCO The primary containment isolation instrumentation for each Function in Table 3.3.6.1-1 shall be OPERABLE.
According to Table 3.3.6.1-1.
ACTIONS ------------------------------NOTES-----------Penetration flow paths may be unisolated intermittently under administrative controls. Separate Condition entry is allowed for each channel. COND IT I ON REOUIRED ACT ION COMPLETION T1 ME A. One or more required channels inoperable.
A.l Place channel in t r' i p. ] 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br /> for 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 Functions with isolation capability not maintained.
B. 1 Restore isolation crJpability, 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (continued)
Columbia GeneraLing Station 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 APPLICABLe S OR OTHER SPE':IFJED CO NO IT IONS REOUIRED CHANNEtS peR TRIP 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 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 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
- 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 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 SYSTEMS 3.6.1.3 Containment Isolation Valves (PCIVs) LCD Each PCIV. except reactor vacuum breukers.
shall be r>10DES 1.2. and 3, associated instrumentation is required to be OPERABLE per LCO 3.3.6.1. *Primary Containment Isolation Instrumentation.*
Acr IONS Penetration flow paths may be unisolaLed intermittently under administrative controls. Separate Condition entry is allowed for each penetration flow path. Enter applicable Conditions and Required Actions for systems made inoperable by PCiVs. 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, -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 automatic valve, closed manual valve, tl1ind flange. or check valve with flow through the valve secured. 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> except for main steam 1 i ne 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br /> for' main steam line (continuPd)
Columbia Generating Station Amendment No. H9 .169 208 1 pcrvs 3.6. 1.l ACIIONS CONDITION REQUIRED ACTION C PL I:.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 I ON REOIJ I RED AU j ON COMPLETfON TIME B. .. 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 a ifec ted penetration flow path by use of at least one closed and de-activated automatic valve. closed manual valve, or b'lind flange. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C.
.... 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 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> except for excess flow clleck va 1 ves (UCVs) 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> 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 T IMF 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 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 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> for hydrostatically tested 1 ine leakage not on a closed system 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 associated Completion Time of Condition A, B. C, or 0 not met in E. 1 AND Be in MODE 3. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> 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 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 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 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)
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
\('FlnNS A (continued) -. -NOTE-----Only applicable to penetration flow paths wi t h two isolation valves. -------------. -------or more penetration flow pat.hs with two SCIVs inoperable.
RFJUIRFD
. -A7.NO TE S [sol d t i 011 devices ill i 9 rl radiation a r'ea S may be verified by use of administrative mr.ans. [solation devices that are locked, sealed, or oUlerwise secured may be verified by use of administrative means.
--Verify ttle affected penetration fl ow path is isolated.
B. Isolat.e the affected penetration FJow path by use of at least one closed and de-activated aut.omatic valve. closed manual valve. or b lind Flange. ..,C IV s . h . ,1 .? COMPurlON 1 1M E Once per 31 days 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> (cant i nued) Columbia Cenpratilllj Station ),6.4.2 2 ArnencJrnent NO. 149,169,199,208
- \" r [IlNS CONDlrrON R e q II i I P l
- t, c t i iJ Il llil (j ds<,ociatf'd Complr:'tion rime of COllclitioll A or B not met i rl MOUE l. 2. or 3. Required Action and 11ssoci ated Completion Time 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 suspend OPDRVs. '-,C I Vc, .().:1 .? COMPU T ION riME 12 flO 1I r S 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> 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 v f? san (j t) 1ind f 1 drl 9 e sin i Cd r' ad i a t ion a r P r1 sma y be ve r i fie c1 by use () f r1 d m i 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' at j v e controls.
Verify each secondary containment 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. 31 clays SR 3.6.4.2.2 Verify the isolation time of each power operated.
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 1 II m b i rJ r, P Ii e r d t. j II 9S t d til) II ATTACHMENT TO LICENSE AMENDMENT NO. FACILITY OPERATING LICENSE NO. DOCKET NO. 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 Technical Specification REMOVE INSERT 3.10.1-1 3.10.1-1
-3Pursuant 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; 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 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. 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. 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: 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. 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. 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 Operation LCD 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: LCD 3.3.6.2. "Secondary Containment Isolation Instrumentation." Functions
- 1. 3, and 4 of Table 3.3.6.2-1; LCO 3.6.4.1. "Secondary Containment"; LCD 3.6.4.2. "Secondary Containment Isolation Valves (SCIVs)";
and LCD 3.6.4.3, "Standby Gas Treatment (SGT) System." APPLICABI MODE 4 with average reactor coolant temperature>
200°F. Columbia Generating Station Amendment No. 149.169 209 ATTACHMENT TO LICENSE AMENDMENT FACILITY OPERATING LICENSE NO. DOCKET NO. 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 Technical Specification REMOVE INSERT 3.3.5.2-4 3.3.5.2-4 3.5.2-3 3.5.2-3
-3Pursuant 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; 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 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. 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. 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: 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. 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. 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 React'.1r Core I'i0lati,)n Cooling System FUNCTION REr}U I RED 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.
Initiation 2 C SR 3.3.5.2.4 NA t: I) 1 1/111 b i,] G i? 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 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 CST. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> 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 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, I RAJ 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