GO2-08-122, Supplement to Adoption of Approved Generic Technical Specification Changes Associated with Containment Isolation Valves

Supplement to Adoption of Approved Generic Technical Specification Changes Associated with Containment Isolation Valves

ML082480298
Person / Time
Site:	Columbia
Issue date:	08/28/2008
From:	Gambhir S Energy Northwest
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GO2-08-122, TAC MD6208
Download: ML082480298 (27)

Text

Sudesh K. Gambhir ENERGY Vice President, Technical Services P.O. Box 968, Mail Drop PE04 NORTHWEST Richland, WA 99352-0968\,

Ph. 509-377-8313 F. 509-377-2354 sgambhir@energy-northwest.com August 28, 2008 G02-08-122 10 CFR 90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

COLUMBIA GENERATING STATION, DOCKET NO. 50-397 SUPPLEMENT TO ADOPTION OF APPROVED GENERIC TECHNICAL SPECIFICATION CHANGES ASSOCIATED WITH CONTAINMENT ISOLATION VALVES

Reference:

Letter G02-07-1 11, dated July 30, 2007, SK Gambhir (Energy Northwest) to NRC, "License Amendment Request for Proposed Changes to Columbia Technical Specifications: Adoption of Approved Generic Technical Specification Changes Associated with Containment Isolation Valves" (TAC No. MD6208)

Dear Sir or Madam:

Via the referenced letter, Energy Northwest proposed a change to the Columbia Generating Station (Columbia) Technical Specifications (TS) to support adoption of a number of Technical Specification Task Force (TSTF) travelers related to Containment Isolation Valves. TSTF-306-A, Revision 2, "Add Action to LCO 3.3.6.1 to give option to isolate penetration" was included as one of the travelers proposed for adoption in the referenced request.

During the NRC review process of the aforementioned submittal, a question with regard to the proposed adoption of TSTF-306-A was raised in that Energy Northwest had not included the recommended Surveillance Requirement (SR) 3.3.6.1.1 requiring a channel check for the proposed addition of Function 6, "Traversing Incore Probe Isolation," to Table 3.3.6.1-1, "Primary Containment Isolation Instrumentation," nor justified its exclusion as a deviation from the traveler. Energy Northwest reviewed the referenced submittal against the recommendations of TSTF-306-A and has concluded that this SR was inappropriately omitted. During this review Energy Northwest also determined that for LCO 3.3.6.1 - Condition A, Function 6.a was not included in the Completion Time as recommended by TSTF-306-A. This deviation from the traveler was also not identified or justified in the referenced submittal.

KA i(

SUPPLEMENT TO ADOPTION OF APPROVED GENERIC TECHNICAL SPECIFICATION CHANGES ASSOCIATED WITH CONTAINMENT ISOLATION VALVES Page 2 The correction of these two issues with the referenced submittal makes the proposed changes consistent with TSTF-306-A. The corrected mark-up of the affected pages are included in Attachment 1. These corrections include 1) the addition of SR 3.3.6.1.1 to Table 3.3.6.1-1 for Functions 6.a and 6.b, and 2) the addition of Function 6.a to the Completion Time of LCO 3.3.6.1 Condition A. The revised TS pages for the changes discussed above are included in Attachment 2. For administrative simplification, includes all of the revised TS pages for this amendment request, inclusive of the two pages affected by this supplement as well as the unaffected pages from the original submittal.

There are no new commitments being made with this submittal.

The changes being made in this supplemental letter meet the intent of TSTF-306-A and do not affect the original evaluation of the proposed changes, including the conclusion of the No Significant Hazards Consideration, submitted via the referenced letter.

Should you have any questions or require additional information regarding this matter, please contact Mr. MC Humphreys, Licensing Supervisor, at 509-377-4025.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the date of this letter.

Repctfully, S3 ambhir Vice President, Technical Services Attachments: 1) Mark-up TS pages

2) Re-typed TS pages cc: EE Collins, Jr. - NRC RIV CF Lyon - NRC NRR NRC Senior Resident Inspector/988C RN Sherman - BPA/1 399 WA Horin - Winston & Strawn

SUPPLEMENT TO ADOPTION OF APPROVED GENERIC TECHNICAL SPECIFICATION CHANGES ASSOCIATED WITH CONTAINMENT ISOLATION VALVES Mark-up TS pages 3.3.6.1-1 3.3.6.1-8 and associated Insert Page 3.3.6.1-A

Primary Containment Isolation Instrumentat~ion 3.3.6.1 3.3 INSTRUMENTATION 3.3.6.1 Primary Containment Isolation Instrumentation LCO 3.3.6.1 The. pri~mary containment isolation. Anstrumentation for 'each Function in Table 3.3.6.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.6.1-1.

ACTIONS -

.Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME

-r"rr-309 A. One or more required A.1 Place channel in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for

f. channels inoperable. trip. Functions 2.a,.

2.c, M 5,d "

Penetration flow paths may be AND 42 ab .

unisolated intermittently under administrative controls. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Functions other than Functions 2.a, 2.c, 60 5.d B. One or more automatic, B.1 Restore isolation I hour Functions with capability.

isolation capability not maintained.

(continued)

Columbia Generating Station 3.3.6.1-1 Amendment No. 4-44 169*

Primary Containment Isolation Instrumentation 3,3.6.1 Table 3.3.6.1-1 (page 4 of 4)

Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR, REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED P'ER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE

5. RHR SDC System Isolation

a. Pump Room Area 3 1 per room F SR 3.3.6.1.3 < 150°F Temperature-High SR 3.3.6.1.4 SR 3.3.6.1.6

b. Pump Room Area 3 1 per roomi F SR 3,3.6.1.3 < 70°F, Ventilation SR 3.3.6.1.4 Differential SR 3.3.6.1.6 Temperature- High

c. Heat Exchanger 3 1 per room F SR. 3.3.6.1.3 Area SR 3.3.6.1.4 Temperature -High SR 3.3.6.1.L.6 Room 505 Area < 140°F Room 507 Area < 160°F Room 605 Area < 150°F Room 606 Area < 140*F

d. Reactor Vessel 3,4.5 2(d) J SR 3.3.6.1.1 > 9.5 inches Water Level - Low, SR 3.3.6.1.2 Level 3 SR 3.3.6.1.4 SR 3.3.6.1.6

e. Reactor Vessel 1.,2,3 1 F SR 3.3.6.1.2 < 135 psig Pressure- High SR 3.3.6.1.4 SR 3.3.6.1.6

f. Manual Initiation 1,2,3 2 G SR 3.3.6.1.6 NA F-S(d) Only one trip system required ii n MODES 4 and 5 with RHR Shutdown Cooling System integrity maintained.

TiS T7F-(WCej: 3.3.6.1 A) 306 Columbia Generating Station 3.3.6.1-8 Amendment No. 149,161 169*

Insert 3.3.6.1-A

6. Traversing Incore Probe Isolation

a. Reactor Vessel Water 1,2,3 2 G SR 3.3.6.1.1 > -58 inches Level - Low, Low SR 3.3.6.1.2 Level 2 SR 3.3.6.1.4 SR 3.3.6.1.6

b. Drywell Pressure 1,2,3 2 G SR 3.3.6.1.1 < 1.88 psig High SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6

SUPPLEMENT TO ADOPTION OF APPROVED GENERIC TECHNICAL SPECIFICATION CHANGES ASSOCIATED WITH CONTAINMENT ISOLATION VALVES Re-typed TS pages 3.3.3.1-3 no changes, included as back side of changed page 3.3.3.1-4 3.3.3.1-4 3.3.6.1-1 3.3.6.1-2 no changes, included as back side of changed page 3.3.6.1-1 3.3.6.1.7 no changes, included as back side of changed page 3.3.6.1-7 3.3.6.1-8 3.6.1.3-1 3.6.1.3-2 3.6.1.3-3 3.6.1.3-4 3.6.1.3-5 3.6.1.3-6 3.6.1.3-7 3.6.1.3-8 3.6.1.3-9 no content change, included due to format changes re-numbering this page and included as back side of new. page in this section 3.6.1.3-10 3.6.1.3-10 no content change, new page in this section due to formatting of changes on preceding pages requiring this page addition and page renumbering 3.6.4.2-1 no changes, included as back side of changed page 3.6.4.2-2 3.6.4.2-2 3.6.4.2-3 proposed change necessitates format change and creation of new page in this section, this page has been included as backside of new page 3.6.4.2-4 3.6.4.2-4

PAM Instrumentation 3.3.3.1 SURVEILLANCE REQUIREMENTS

---

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

1. These SRs apply to each Function in Table 3.3.3.1-1.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the other required channel(s) in the associated Function is OPERABLE.

SURVEILLANCE FREQUENCY SR 3.3.3.1.1 Perform CHANNEL CHECK. 31 days SR 3.3.3.1.2 Deleted SR 3.3.3.1.3 Perform CHANNEL CALIBRATION for 18 months Functions 1, 2, 4, 5, and 10.

SR 3.3.3.1.4 Perform CHANNEL CALIBRATION for 24 months Functions 3, 6, and 7.

Columbia Generating Station 3.3.3.1-3 Amendment No. .

149.169.17n 189

PAM Instrumentation 3.3.3.1 Table 3.3.3.1-1 (page 1 of 1)

Post Accident Monitoring Instrumentation CONDITIONS REFERENCED

. REOUIRED FROM REQUIRED FUNCTION CHANNELS ACTION D.1

1. Reactor Vessel Pressure 2 E

2. Reactor Vessel Water Level

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

b. -310 inches to -110 inches 2 E

3. Suppression Pool Water Level

a. -25 inches to +25 inches 2 E

b. 2 ft to 52 ft 2 E

4. Suppression Chamber Pressure 2 E

5. Drywell Pressure.

a. -5 p'sig to +3 psig 2 E

b. 0 psig to 25 psig 2 E

c. 0 psig to 180 psig 2 E 6,. Primary Containment Area Radiation 2 F

7. Penetration Flow Path PCIV Position 2 per penetration E flbw path (a)(b)

8. Deleted 9.. Deleted

10. ECCS Pump Room Flood Level 5 E (a) Not required for isolation valves whose associated penetration flow path is isolated by at least one closed and de-activated automatic valv*e, closed manual valve, blind flange, or check. v.alve with flow through the valve secured.. ...

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

Columbi-a Genera,ting S'tation 3 .3.,3 .,11-,4 ý'Amendment No.. 149,169,48ýý

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

APPLICABILITY: According to Table 3.3.6.1-1.

ACTIONS

---

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

1. Penetration flow paths may be unisolated intermittently under administrative control s.

2. Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Place channel in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for channels inoperable, trip. Functions 2.a, 2.c, 5.d, 6.a and 6.b AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Functions other than Functions 2.a, 2.c, 5.d, 6.a and 6.b B. One or more automatic B.1 Restore isolation 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Functions with capability.

isolation capability not maintained.

(continued)

Columbia Generat-ing Sta~tioon 3.3..6.1-I1 , AmendmentNo. 149,169

Primary Containment Isolation Instrumentation 3.3.6.1 ACTIONS .

CONDITION . REQU-IRED ACTION - COMPLETION TIME C. Required Action, and. C..1' Enter the Condition Immediately associated Completion referenced-.i-.n.n Time of Condition A Table 3.3.6.1-1 for or B not met. the channel.

D. As required by D.1 Isolate associated 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Required Action C.1 main steam line and referenced/in (MSL).

Table 3.3.6.1-1.

OR D.2.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND D.2.2 Be in MODE 4. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> E. As required by E.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Required Action.C.1 and referenced in Table 3.3.6.1-1.

F. As required by F.1 Isolate the affected 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Required Action C.1 penetration flow and referenced in path(s).

Table 3.3.6.1-1.

G. As required by G.1 Isolate the affected 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Required Action C.I penetration flow and referenced in path(s).

Table 3.3.6.1-1.

(continued)

Columbia Generatin'g Station: 3A1 8.3ý..6.,.1 -.2 [Amendment, Noý. 44 .169

Primary.Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 3 of 4)

Primar-y Containment..Isol-ati.on..Instrumentation APPLICABLE CONDITIONS MODES OR 'REQUIRED- REFERENCED..

OTHER CHANNELS FROM FUNCTIONSPECIFIED. PERTRIP REQUIRED, SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.;1 REQUIREMENTS VALUE

4. RWCU System Isolation (continued)

b. Differential 1,2,3 1 F SR 3.3.6.1.2 < 46.5 seconds Flow-Time Delay SR 3.3. 6. 1.5 SR 3.3.6.1.6

c. Bl owdowh Flow-: 1,2,3>' F SR 3.3.6.1.1 (271:7 gpm High SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.7

d. Heat Exchanger 1,2,3 F SR 3.3.6.1.3 < 160'F Room Area SR 3.3.6.1.4 Temperature - High SR 3.3.6.1.6

a. Heat Exchanger 1,2,3 1 F SR 3.3.6.1.3 < 70'F Room Area SR 3.3.6.1.4 Ventilation SR 3.3.6.1.6 Differential, Temperature- High

f. Pump Room Area . 1,2,3 1 per room F SR 3.3.6.1.3 < 180'F Temperature - High SR 3.3. 6. 1'.4 SR 3.3.6.1.6

g. Pump Room Area 1,2,3 1 per room F " SR 3.3.6.1.3 < IO0°F Ventilation SSR 3.3.6.1.4 Differential SR 3.3.6.1.6 Temperature - High

< 180'F

h. RWCU/RCIC Line 1,2,3 1 F SR 3.3.6.1.3 Routing Area SR 3.3.6.1.4 Temperature-High SR 3. 3. 6. 1 .6

i. RWCU Line Routing 1,2,3 1 per room F SR 3.3.6.1.3 Area SR 3.3.6.1.4 Temperature - High SSR 3.3.6.1.6 Room 409, 509 K 175'F Areas Room 408, 511 < 180'F Areas -

j. Reactor Vessel 1,2,3 2 F SR 3.3.6.1.2 > -58 inches Water Level - Low SR 3.3.6.1.4 Low, Level 2 SR 3.3.6.1.6

k. SLC System 1,2.3 Z( c) I SR 3.3.6.1.6 NA Initiation

1. Manual Initiation 1.2.3 2 G SR 3.3.6.1.6 NA (continued)

(c) SLC System Initiation only inputs into one of the two trip systems.

Col'umbia Generating -S-t-ation 3". 31.. 6:.l1- 7 Amendment: No.:,149,169,172 199

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

Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM.

SPECIF:IED PER TRIP REQUIRED. SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE

5. RHR SDC System Isolation

a. Pump: Room Area ,3 1 p.er room,. F SR 3.3.6.1.3 < 150'F Temperature- High SR 3.3.6.1.4 SR '3.3.6.1.6

b. Pump Room Area 3 1 per room F SR 3.3.6.1.3 < 70°F Ventilation SR 3.3.6.1.4 Differential SR 3.3.6.1.6 Temperature- High

c. Heat Exchanger 3 1 per room F SR 3.3.6.1.3 Area SR 3.3.6.1.4 Temperature- High SR 3.3.6.1.6 Room 505 Area < 140'F Room .507 Area < 160'F Room 605 Area < 150'F Room 606 Area < 140'F

d. Reactor Vessel 3,4,5 2 (d) SR 3.3.6.1.1 > 9.5 inches Water Level - Low, SR 3.3.6. 1.2 Level 3 SR 3.3.6.1.4 SR 3.3.6.1.6

e. Reactor Vessel 1.2,3 1 F SR 3.3.6.1.2 < 135, p'sig Pressure - High SR 3.3.6.1.4 SR 3.3.6.1.6

.f. Manual 'Initiati~on .

1,2 :3 G SR 3.3.6.1.6 'NA

6. Traversing Incore Probe Isolation

a. Reactor Vessel, 1,2,3 2 G SR 3.3.6.1.1 > -58 i.nches Water Level' - Low SR 3.3.6.1.2 Low, Level 2 SR .3.3.3 6.1.4 SR 3.3.6.1.6

b. Drywell Pressure - 1 .2,3 :2 G . SR 3.3.6.1.1 < 1.88 psig High SR 3.3.6.1.2 SR 3.3.6.1.4 SR .3.3.6.1.6 (d) Only one trip system required i'nMODES 4 and 5 with RHR Shutdown Cooling System integ rity maintained.

Col umbia Generating Station . 3 . 6 .1 .'A'm'en:'d'm'en t No. 444, 69

PCIVs 3.6.1.3 3.6 CONTAINMENT SYSTEMS 3.6.1.3 Primary Containment Isolation Valves (PCIVs)

LCO 3.6.1.3 Each PCIV, except reactor building-to-suppression chamber

.vacuum breakers, shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, When associated instrumentation is: required to be OPERABLE per LCO 3.3.6.1, "Primary Containment Isolation Instrumentation."

ACTIONS

---

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

1. Penetration flow paths may be unisolated 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 overall containment leakage rate acceptance criteria.

CONDITION REQUIRED ACTION COMPLETION TIME A.----------- NOTE ---------- A.1 Isolate the affected 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> except Only applicable to. penetration flow path, for main steam penetration flow paths by use of at least line with two PCIVs. one closed and de-activated AND automatic valve, One or more closed manual valve, 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for penetration flow paths blind flange, or main steam line w.ith one PCIV . . check..valve wi.th flow. . .

inoperable for reasons thrQugh the valve other than secured.

Condition D.

AND (continued)

Col.umbi.a Ge-neratiing ,Statio*n3 3ý:.ý6..1 .13 -.I Amendment No., 149:,1.69

PCIVs 3.6.1.3 ACT.IONS -

CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 --- NOTES------ ----

1. Isolatidn 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.. i sol ati on devices outside primary containment AND Prior to entering MODE 2 or 3 from MODE 4 if primary 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. 6.4.1:.3- 2. "ý. .',Amendment. No'. 1494'-19

PCIVs 3.6.1.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.---------- NOTE--------- -B..1 Isolate the affected 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Only applicable, to penetration flow path penetration flow paths, by *use of at:least with two PCIVs. one closed and

---

--....... .de-activated.

automatic va,lve One or more closed manual valve, penetration flow paths or blind flange.

with two PCIVs inoperable for reasons other than Condition D.

C.---------- NOTE ---------- C.1 Isolate the ýaffected 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> except Only applicable to penetration flow path for excess flow penetration flow paths by use of at least check valves with only one PCIV. one closed and (EFCVs) de-activated!

automatic vaIve, AND One or more closed manua'l valve, penetration flow paths or blind flange. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for with one PCIV EFCVs inoperable foh reasons AND other than Condition D.

(continued)

Columbi.a Generating Station 3. 6J.1.3, Amendment No. 149,169

PCIVs 3.6.1.3 ACT..ION S CONDITION j REWUIRED ACTI'N COMPLETION IME C. (continued) C.2 *-------- NOTES-----

• 1. Isolatiodn devices in high radiation areas may be verified by use of administrative, means.

2. Isolatio~n 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 AND Prior to entering MODE 2 or 3 from MODE 4 if pri mary 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 :.6' . .1I.-3 L!

4ý  ;--Amendmeý'nt No,'. 149,169

PCIVs 3.6.1.3 ACTIONS CONDITION REOUJRED ACTI:ON COMPLETION TIME D. One or more secondary D'.I Restore leakage rate 4 hour~s for containment bypass to~within limit, hydrostatically leakage rate,!MSIV tested line leakage rate, or , leakage not on hydrostatically tested a closed system lines leakage rate not within limit. AND 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for secondary containment bypass leakage AND 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for MSIV leakage AND 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for hydrostatically tested line leakage on a closed system E. Required Action and E.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A, AND B, C, or D not met in

,MODE 1, 2, or 3. E.2 Be in MODE 4. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> (continued)

Columbia Generating Station 3. 6.. 1 . 3;- 5 Amendment No. 149,1,69

PCIVs 3.6.1.3 ACT IONS ..,_... ........... _ . _ _ _ _ . _

CONDITIO'N REQUIRED"ACTION COMPLETION TIME F. Required Action and F.1 Initiate action to Immediately associated Completion' suspend ope:rations Time of Condiltion A, witha potential for.

B, C, or D not met for d,rbining the reactor PCIV(s) required to 'be vessel (OeDRVs).

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

Columbia Genera'tihg Station 3 . 6.1,-3-6 Amendment No. 1ýýJ,ýUj A 0- 1

PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 1 "3 "'N 6 ".

3 ". '1 7 7 -- - - ---- "-1 -

OT E - . . . . . -.

Not required.,,to be'me.twhen the .24 inch.

and 30 inch prima~rycontainment purge valves are openfobr !inerting, de-inerting,;pressure control, ALARA or air quality considerations for personnel entry, or Surveillances that require the valves to be open.

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

SR 3.6.1.3.2 -------------------NOTES-----------------

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

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

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

(continued)

Columbia Gen~erati.ng ,Station 3-. 6. 1-.. 3- 7 Amendment No. 149,,169

PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS ....... ..... ____"

SURVEILLANCE FREQUENCY SR 3.6.1.3.3 --- NOTES- -----------------

.1. Valves and blind f-langes i.n high radiation areas may be verified by use of administrative means.

-2.. Not required to-be met for...PCIVs that are open under administrative control.s.

Verify each primary containment isolation Prior to manual valve and blind flange that is entering MODE .2

,located inside primary containment and or 3 from

'not locked, sealed, or otherwise secured MODE 4 if and is required to be closed during primary accident conditions is closed., containment was de-inerted while in MODE 4, if not performed within the previous 92 days SR 3.6.1.3.4 Verify continuity of the traversing 31 days

,incore probe (TIP) shear isolation valve explosive charge.

SR 3.6.1.3.5 .Verify the isolation time of each power. In accordance

ýoperated, automatic PCIV, except MSIVs, with the is.within limits. .. Inservice Testing Program (continued)

Columbia Generating Station 3.6.1.3-8 Amendment No.

449,4169, 1709 ,1' 199

PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS _ _ _ ,_

SURVEILLANCE FREQUENCY SR 3.6.1.3.6 Verify the isolation time of each MSIV is In accordance

> 3 seconds and K 5 seconds.. with the I1 Inservice Testing Program SR 3.6.1.3.7 ýVerify each automatic PCIV actuates to 24 months the isolation position on an actual or simulated isolation signal.

SR 3.6.1.3.8 Verify a representative sample of reactor 24 months instrument line EFCVs actuate to the isolation positidn on an actual or simulated instrument line break signal.

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

Columbia Generating. Station 3.6.1.3-9 Amendment No. 149.169 199

PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.3.11 Verify leakage rate through each MSIV is In accordance

< 16.0 scfh when tested at > 25.0 psig. with the Primary Containment Leakage Rate Testing Program SR 3.6.1.3.12 Verify combined leakage rate through In accordance hydrostatically tested lines that with the penetrate the primary containment is Primary within limits. Containment Leakage Rate Testing Program Columbia Generating Station 3.6.1.3-10 Amendment No. I

SCIVs 3.6.4.2 3.6 CONTAINMENT SYSTEMS 3..6.14.2 .Secondary, Contain.me}nt I.solat.ion Va.lves,.(.SCIVs LCO 3.6-.4-.2 Each SCIV shall. be-OPERABLE.

APPLICABILITY: MODES I, 2;, and 3,'

• During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS I

---

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

1. Penetration flow paths may be unisolated 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 SCIVs.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Isolate the affected 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> penetration flow paths penetration flow path with one SCIV by use of at least inoperable, one closed and de-activated automatic valve, closed manual valve, or blind flange.

AND (continued)

Columbia Generating Station 3.6.4.2-1 Amendment No. H9,H9 199

SCIVs 3.6.4.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.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 otherwis'e secured may be verified by use of administrative means Verify the affected Once per 31 days penetration flow path is isolated.

B. --------- NOTE- -------- B.1 Isolate the affected 4hours Only applicable to penetration flow path penetration flow paths by use of at least with two isolation one closed and valves. de-activated automatic valve, closed manual valve, One or more or blind flange.

penetration flow paths with two SCIVs inoperable.

(continued)

Columbia Generating Station 3.6.4.2-2 Amendment No. 149,169,199

I I .

SCIVs 3.6.4.2 ACTIONS CONDITION REHUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A AND or B not met in MODE 1, 2, or 3. C.2 Be in MODE 4. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> D. Required Action and D.1 Initiate action Immediately associated Completion to suspend Time of Condition A OPDRVs.

or B not met during OPDRVs.

Columbia Generating Station 3.6.4.2-3 Amendment No. H9,H9 199

SCIVs 3.6.4.2 SIrnVFTIIANCF PFflIiIRFMFN~T~

-,IIPVFTLIAN(-F RFnHTRFMFNT-,

SURVEILLANCE FREQUENCY SR 3.6.4.2.1 ------------------- NOTES-----------------

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

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

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

SR 3.6.4.2.2 Verify the isolation time of each power In accordance operated, automatic SCIV is within with the limits. Inservice Testing Program I

SR 3.6.4.2.3 Verify each automatic SCIV actuates to 24 months the isolation position on an actual or simulated automatic isolation signal.

j 3.6.4.2-4 Columbia Generating Station Amendment No. I