ML091540083
| ML091540083 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 07/31/2009 |
| From: | Balwant Singal Plant Licensing Branch IV |
| To: | Muench R Wolf Creek |
| Singal, Balwant K, NRR/DORL 301-415-3016 | |
| References | |
| TAC MD9469 | |
| Download: ML091540083 (58) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 31, 2009 Mr. Rick A. Muench President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KS 66839
SUBJECT:
WOLF CREEK GENERATING STATION -ISSUANCE OF AMENDMENT RE:
REVISION TO TECHNICAL SPECIFICATION (TS) 3.3.2, "ENGINEERED SAFETY FEATURE ACTUATION SYSTEM (ESFAS) INSTRUMENTATION" AND TS 3.7.2, "MAIN STEAM ISOLATION VALVES (MSIVs)," AND ADDITION OF NEW TS 3.7.19, "SECONDARY SYSTEM ISOLATION VALVES (SSIVs)"
Dear Mr. Muench:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 184 to Renewed Facility Operating License No. NPF-42 for the Wolf Creek Generating Station. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated August 14, 2008, as supplemented by letter dated April 10, 2009.
The amendment revises TS 3.7.2, "Main Steam Isolation Valves (MSIVs)" to add the MSIV bypass valves to the scope of this TS, revises footnote (i) and adds footnote (I) in Table 3.3.2-1 of TS 3.3.2, "Engineered Safety Feature Actuation System (ESFAS) Instrumentation," for consistency with the revised applicability of Limiting Condition for Operation (LCO) 3.7.2, and adds a new TS 3.7.19, "Secondary System Isolation Valves (SSIVs)," to include an LCO, conditions/required actions, and surveillance requirements for the steam generator blowdown isolation valves and steam generator blowdown sample isolation valves.
R. A. Muench
- 2 A copy of our related Safety Evaluation is enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely, b9\\.lw~ L~\\v.:~
Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-482
Enclosures:
- 1. Amendment No. 184 to NPF-42
- 2. Safety Evaluation cc w/encls: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 184 License No. NPF-42
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Wolf Creek Generating Station (the facility)
Renewed Facility Operating License No. NPF-42 filed by the Wolf Creek Nuclear Operating Corporation (the Corporation), dated August 14, 2008, as supplemented by letter dated April 10, 2009, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-42 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 184, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. The Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3.
The license amendment is effective as of its date of issuance and shall be implemented prior to startup from refueling outage 17.
FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Markley, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: Jul y 31, 2009
ATTACHMENT TO LICENSE AMENDMENT NO. 184 RENEWED FACILITY OPERATING LICENSE NO. NPF-42 DOCKET NO. 50-482 Replace the following pages of the Renewed Facility Operating License No. NPF-42 and Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
The corresponding overleaf pages are provided to maintain document completeness.
Renewed Facility Operating License REMOVE INSERT 4
4 Technical Specifications REMOVE INSERT REMOVE INSERT iii 3.3-32 3.3-33 3.7-5 3.7-6 3.7-7 3.7-8 3.7-9 3.7-10 3.7-11 3.7-12 3.7-13 3.7-14 3.7-15 3.7-16 3.7-17 3.7-18 3.7-19 3.7-20 3.7-21 3.7-22 iii 3.3-32 3.3-33 3.7-5 3.7-6 3.7-7 3.7-8 3.7-9 3.7-10 3.7-11 3.7-12 3.7-13 3.7-14 3.7-15 3.7-16 3.7-17 3.7-18 3.7-19 3.7-20 3.7-21 3.7-22 3.7-23 3.7-23 3.7-24 3.7-25 3.7-26 3.7-27 3.7-28 3.7-29 3.7-30 3.7-31 3.7-32 3.7-33 3.7-35 3.7-36 3.7-37 3.7-38 3.7-39 3.7-40 3.7-41 3.7-42 3.7-24 3.7-25 3.7-26 3.7-27 3.7-28 3.7-29 3.7-30 3.7-31 3.7-32 3.7-33 3.7-34 3.7-36 3.7-37 3.7-38 3.7-39 3.7-40 3.7-41 3.7-42 3.7-43 3.7-44 3.7-45
4 (5)
The Operating Corporation, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6)
The Operating Corporation, 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.
C.
This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations 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 Operating Corporation is authorized to operate the facility at reactor core power levels not in excess of 3565 megawatts thermal (100% power) in accordance with the conditions specified herein.
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 184, and the Environmental Protection Plan contained in Appendix S, both of which are attached hereto, are hereby incorporated in the license. The Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3)
Antitrust Conditions Kansas Gas & Electric Company and Kansas City Power & Light Company shall comply with the antitrust conditions delineated in Appendix C to this license.
(4)
Environmental Qualification (Section 3.11, SSER #4, Section 3.11, SSER #5)*
Deleted per Amendment No. 141.
- The parenthetical notation following the title of many license conditions denotes the section of the supporting Safety Evaluation Report and/or its supplements wherein the license condition is discussed.
Renewed License No. NPF-42 Amendment No. 184
TABLE OF CONTENTS 3.7 PLANT SYSTEMS 3.7-1 3.7.1 Main Steam Safety Valves (MSSVs) 3.7-1 3.7.2 Main Steam Isolation Valves (MSIVs) and MSIV Bypass Valves..... 3.7-5 3.7.3 Main Feedwater Isolation Valves (MFIVs) and Main Feedwater Regulating Valves (MFRVs) and MFRV Bypass Valves 3.7-9 3.7.4 Atmospheric Relief Valves (ARVs) 3.7-13 3.7.5 Auxiliary Feedwater (AFW) System 3.7-15 3.7.6 Condensate Storage Tank (CST) 3.7-18 3.7.7 Component Cooling Water (CCW) System..
3.7-20 3.7.8 Essential Service Water System (ESW)........................................... 3.7-22 3.7.9 Ultimate Heat Sink (UHS) 3.7-24 3.7.10 Control Room Emergency Ventilation System (CREVS) 3.7-26 3.7.11 Control Room Air Conditioning System (CRACS) 3.7-29 3.7.12 Emergency Core Cooling System (ECCS) Pump Room Exhaust Air Cleanup System - Not Used 3.7-32 3.7.13 Emergency Exhaust System (EES) 3.7-33 3.7.14 Penetration Room Exhaust Air Cleanup System (PREACS)
Not Used 3.7-37 3.7.15 Fuel Storage Pool Water Level......................................................... 3.7-38 3.7.16 Fuel Storage Pool Boron Concentration....................
3.7-39 3.7.17 Spent Fuel Assembly Storage 3.7-41 3.7.18 Secondary Specific Activity..
3.7-43 3.7.19 Secondary System Isolation Valves (SSIVs) 3.7-44 3.8 ELECTRICAL POWER SySTEMS........................................................... 3.8-1 3.8.1 AC Sources - Operating............................................
3.8-1 3.8.2 AC Sources - Shutdown 3.8-18 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air 3.8-21 3.8.4 DC Sources - Operating.................................................................... 3.8-24 3.8.5 DC Sources - Shutdown 3.8-28 3.8.6 Battery Cell Parameters..
3.8-30 3.8.7 Inverters - Operating 3.8-34 3.8.8 Inverters - Shutdown 3.8-35 3.8.9 Distribution Systems - Operating.............
3.8-37 3.8.10 Distribution Systems - Shutdown.....
3.8-39 3.9 REFUELING OPERATIONS..................................................................... 3.9-1 3.9.1 Boron Concentration 3.9-1 3.9.2 Unborated Water Source Isolation Valves 3.9-2 3.9.3 Nuclear Instrumentation 3.9-3 3.9.4 Containment Penetrations 3.9-5 3.9.5 Residual Heat Removal (RHR) and Coolant Circulation - High Water Level.................................................... 3.9-7 3.9.6 Residual Heat Removal (RHR) and Coolant Circulation - Low Water Level 3.9-9 Wolf Creek - Unit 1 iii Amendment No. 123, 132, 134, 163, 171, 4-7-7, 184
ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 2 of 5)
Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE (a)
- 3.
Containment Isolation
- a.
Phase A Isolation (1 ) Manual Initiation 1,2,3,4 2
B SR 3.3.2.8 NA (2) Automatic 1,2,3.4 2 trains C
SR 3.3.2.2 NA Actuation Logic SR 3.3.2.4 and Actuation SR 3.3.2.6 Relays (3) Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.
- b.
Phase B Isolation (1 ) Manual Initiation 1,2,3,4 2 per train, B
SR 3.3.2.8 NA 2 trains (2) Automatic 1,2,3,4 2 trains c
SR 3.3.2.2 NA Actuation Logic SR 3.3.2.4 and Actuation SR 3.3.2.6 Relays (3) Containment 1,2,3 4
,,28.3 psig Pressure -
SR 3.3.2.5 High 3 SR 3.3.2.9 SR 3.3.2.10
- 4.
Steam Line Isolation
- a.
Manual Initiation 2
F SR 3.3.2.8 NA
- b.
Automatic Actuation 2 trains G
SR 3.3.2.2 NA Logic and Actuation SR 3.3.2.4 Relays (SSPS)
- c.
Automatic Actuation 2 trains G
SR 3.3.2.6 NA Logic (MSFIS)
- d. Containment Pressure 3
" 18.3 psig
- High 2 SR 3.3.2.5 SR 3.3.2.9 SR 3.3.2.10 (continued)
(a)
The Allowable Value defines the Limiting Safety System Setting. See the Bases for the Trip Setpoints.
(i)
Except when all MSIVs are closed and de-activated; and all MSIV bypass valves are closed and de-activated, or closed and isolated by a closed manual valve, or isolated by two closed manual valves.
(I)
Except when all MSIVs are closed and de-activated.
Wolf Creek - Unit 1 3.3-32 Amendment No. 123, 175, 183, 184
ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 3 of 5)
Engineered Safety Feature Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE (a)
- 4.
Steam Line Isolation (continued)
- e.
Steam Line Pressure (1 ) Low 1,2(i),3(b)(i) 3 per steam line D
SR 3.3.2.1 SR 3.3.2.5 SR 3.3.2.9 SR 3.3.2.10
~ 571 psig(c)
(2)
Neg ative Rate High 3(g)(i) 3 per steam line D
SR 3.3.2.1 SR 3.3.2.5 SR 3.3.2.9 SR 3.3.2.10
" 125(h) psi
- 5.
Turbine Trip and Feedwater Isolation
- a.
Automatic Actuation Logic and Actuation Relays (SSPS) 1,20>,30>
2 trains G
SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.6 NA
- b.
Automatic Actuation Logic (MSFIS) 1,2(k),3(k) 2 trains G
SR 3.3.2.6 NA
- c.
SG Water Level -High High (P-14) 1,20>
4 perSG SR 3.3.2.1 SR 3.3.2.5 SR 3.3.2.9 SR 3.3.2.10
,,79.7% of Narrow Range Instrument Span
- d.
Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.
(continued)
(a) The Allowable Value defines the Limiting Safety System Setting. See the Bases for the Trip Setpoints.
(b) Above the P-11 (Pressurizer Pressure) Interlock and below P-11 unless the Function is blocked.
(c) Time constants used in the lead/lag controller are t, ~ 50 seconds and t2 " 5 seconds.
(g) Below the P-11 (Pressurizer Pressure) Interlock; however, may be blocked below P-11 when safety injection on low steam line pressure is not blocked.
(h) Time constant utilized in the rate/lag controller is ~ 50 seconds.
(i) Except when all MSIVs are closed and de-activated; and all MSIV bypass valves are closed and de-activated, or closed and isolated by a closed manual valve, or isolated by two closed manual valves.
0> Except when all MFIVs are closed and de-activated; and all MFRVs are closed and de-activated or closed and isolated by a closed manual valve; and all MFRV bypass valves are closed and de-activated, or closed and isolated by a closed manual valve, or isolated by two closed manual valves.
(k) Except when all MFIVs are closed and de-activated.
Wolf Creek - Unit 1 3.3-33 Amendment No. 123, 132, 176, 177,
~,184
MSIVs and MSIV Bypass Valves 3.7.2 3.7 PLANT SYSTEMS 3.7.2 Main Steam Isolation Valves (MSIVs) and MSIV Bypass Valves LCO 3.7.2 Four MSIVs and their associated actuator trains, and four MSIV bypass valves shall be OPERABLE.
NOTE---------------------------------------------
- 1.
All MSIVs and their associated actuator trains may be inoperable in MODES 2 and 3 when closed and de-activated.
- 2.
One or more IIJ1SIV bypass valves may be inoperable when closed and de-activated, closed and isolated by a closed manual valve, or isolated by two closed manual valves.
APPLICABILITY:
MODE 1, 2, and 3.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One MSIV actuator train inoperable.
A.1 Restore MSIV actuator train to OPERABLE status.
7 days B.
Two MSIV actuator trains inoperable for different MSIVs when the inoperable actuator trains are not in the same separation group.
B.1 Restore one MSIV actuator train to OPERABLE status.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> C.
Two MSIV actuator trains inoperable when the inoperable actuator trains are in the same separation group.
C.1 Restore one MSIV actuator train to OPERABLE status.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (continued)
Wolf Creek - Unit 1 3.7-5 Amendment No. 123, 171, 184
3.7.2 ACTIONS (continued)
CONDITION D.
Two actuator trains for one MSIV inoperable.
E.
Three or more MSIV actuator trains inoperable.
OR Required Action and associated Completion Time of Condition A, B, or C not met.
F.
One MSIV inoperable in MODE 1.
G. Required Action and associated Completion Time of Condition F not met.
H.
N0 TE--------------
Separate Condition entry is allowed for each MSIV bypass valve.
One or more MSIV bypass valves inoperable.
MSIVs and MSIV Bypass Valves REQUIRED ACTION D.1 Declare the affected MSIV inoperable.
E.1 Declare each affected MSIV inoperable.
F.1 Restore MSIV to OPERABLE status.
G.1 Be in MODE 2.
H.1 Close or isolate MSIV bypass valve.
AND H.2 Verify MSIV bypass valve is closed or isolated.
COMPLETION TIME Immediately Immediately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 6 hours 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Once per 7 days (continued)
Wolf Creek - Unit 1 3.7-6 Amendment No. 123, 171, 184
3.7.2 MSIVs and MSIV Bypass Valves ACTIONS (continued)
CONDITION I.
NOTE-------------
Separate Condition entry is allowed for each MSIV.
One or more MSIV inoperable in MODE 2 or 3.
J.
Required Action and associated Completion Time of Condition H or I not met.
REQUIRED ACTION COMPLETION TIME 1.1 Close MSIV.
8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> AND 1.2 Verify MSIV is closed.
Once per 7 days J.1 Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND J.2 Be in MODE 4.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.2.1
NOTE--------------------------------
Only required to be performed in MODES 1 and 2.
Verify the isolation time of each MSIV is within limits.
In accordance with the Inservice Testing Program SR 3.7.2.2
NOTE-------------------------------
Only required to be performed in MODES 1 and 2.
Verify each actuator train actuates the MSIV to the isolation position on an actual or simulated actuation signal.
18 months (continued)
Wolf Creek - Unit 1 3.7-7 Amendment No. 123, 171, 174, 184
3.7.2 MSIVs and MSIV Bypass Valves SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.7.2.3 Verify each MSIV bypass valve actuates to the isolation position on an actual or simulated actuation signal.
18 months SR 3.7.2.4 Verify isolation time of each MSIV bypass valve is within limit.
In accordance with the Inservice Testing Program Wolf Creek - Unit 1 3.7-8 Amendment No. 184
MFIVs and MFRVs and MFRV Bypass Valves 3.7.3 3.7 PLANT SYSTEMS 3.7.3 Main Feedwater Isolation Valves (MFIVs) and Main Feedwater Regulating Valves (MFRVs) and MFRV Bypass Valves LCO 3.7.3 Each MFIV and its associated actuator trains, MFRV and MFRV bypass valve for the four main feedwater lines shall be OPERABLE.
APPLICABILITY:
MODE 1 MODES 2 and 3, except for each affected main feedwater line when:
- a.
The MFIV is closed and deactivated; or
- b.
The MFRV is closed and deactivated or closed and isolated by a closed manual valve; and the MFRV bypass valve is either closed and deactivated, closed and isolated by a closed manual valve, or isolated by two closed manual valves.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One MFIV actuator train inoperable.
A.1 Restore MFIV actuator train to OPERABLE status.
7 days B.
Two MFIV actuator trains inoperable for different MFIVs when the inoperable actuator trains are not in the same separation group.
B.1 Restore one MFIV actuator train to OPERABLE status.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> C.
Two MFIV actuator trains inoperable when the inoperable actuator trains are in the same separation group.
C.1 Restore one MFIV actuator train to OPERABLE status.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (continued)
Wolf Creek - Unit 1 3.7-9 Amendment No. 12d, 171, 177, 184
3.7.3 ACTIONS (continued)
CONDITION D.
Two actuator trains for one MFIV inoperable.
E.
Three or more MFIV actuator trains inoperable.
OR Required Action and associated Completion Time of Condition A, B, or C not met.
F.
NOTE-------------
Separate Condition entry is allowed for each MFIV.
One or more MFIVs inoperable.
G. --------------NOTE-------------
Separate Condition entry is allowed for each MFRV.
One or more MFRVs inoperable.
MFIVs and MFRVs and MFRV Bypass Valves REQUIRED ACTION 0.1 Declare the affected MFIV inoperable.
E.1 Declare each affected MFIV inoperable.
F.1 Close MFIV.
AND F.2 Verify MFIV is closed.
G.1 Close or isolate MFRV.
AND G.2 Verify IVIFRV is closed or isolated.
COMPLETION TIME Immediately Immediately 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Once per 7 days 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Once per 7 days (continued)
Wolf Creek - Unit 1 3.7-10 Amendment No. 123, 171, 174, 177, 184
3.7.3 MFIVs and MFRVs and MFRV Bypass Valves ACTIONS (continued)
CONDITION H.
NOTE-------------
Separate Condition entry is allowed for each MFRV bypass valve.
One or more MFRV bypass valves is inoperable.
I.
Two valves in the same flow path inoperable.
J.
Required Action and associated Completion Time of Condition F, G, H, or I not met.
REQUIRED ACTION H.1 Close or isolate MFRV bypass valve.
AND H.2 Verify MFRV bypass valve is closed or isolated.
1.1 Isolate affected flow path.
J.1 Be in MODE 3.
AND J.2 Be in MODE 4.
COMPLETION TIME 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Once per 7 days 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 6 hours 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.7.3.1
NOTE--------------------------------
Only required to be performed in MODES 1 and 2.
Verify the isolation time of each MFIV, MFRV and MFRV bypass valve is within limits.
FREQUENCY In accordance with the Inservice Testing Program (continued)
Wolf Creek - Unit 1 3.7-11 Amendment No. 123, 171, 174, 177, 184
MFIVs and MFRVs and MFRV Bypass Valves 3.7.3 SURVEILLANCE REQUIRMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.7.3.2
NOTE--------------------------------
Only required to be performed in MODES 1 and 2.
Verify each actuator train actuates the MFIV to the isolation position on an actual or simulated actuation signal.
18 months SR 3.7.3.3
NOTE--------------------------------
Only required to be performed in MODES 1 and 2.
Verify each MFRV and MFRV bypass valve actuates to the isolation position on an actual or simulated actuation signal.
18 months Wolf Creek - Unit 1 3.7-12 Amendment No. 123, 171, 177, 184 I
3.7.4 ARVs 3.7 PLANT SYSTEMS 3.7.4 Atmospheric Relief Valves (ARVs)
LCO 3.7.4 Four ARV lines shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, and 3.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One ARV line inoperable for reasons other than excessive leakage.
A.1 Restore required ARV line to OPERABLE status.
7 days B.
Two ARV lines inoperable for reasons other than excessive leakage.
B.1 Restore all but one required ARV line to OPERABLE status.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> C.
Three or more ARV lines inoperable for reasons other than excessive leakage.
C.1 Restore all but two ARV lines to OPERABLE status.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (continued)
Wolf Creek - Unit 1 3.7-13 Amendment No. 123, 127, 155, 171, 177, 184
3.7.4 ARVs ACTIONS (continued)
CONDITION D.
With one or more of the ARVs inoperable because of excessive seat leakage.
E.
Required Action and associated Completion Time not met.
REQUIRED ACTION 0.1 Initiate action to close the associated block valve(s).
AND 0.2 Restore ARV(s) to OPERABLE staus.
E.1 Be in MODE 3.
AND E.2 Be in MODE 4.
COMPLETION TIME Immediately 30 days 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 12 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Verify one complete cycle of each ARV.
In accordance with the Inservice Testing Program SR 3.7.4.2 Verify one complete cycle of each ARV block valve.
18 months Wolf Creek - Unit 1 3.7-14 Amendment No. 123, 127, 155, 171,177, 184
3.7.5 AFW System 3.7 PLANT SYSTEMS 3.7.5 Auxiliary Feedwater (AFW) System LCO 3.7.5 Three AFW trains shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, and 3.
ACTIONS
NOTE----------------------------------------------------------
LCO 3.0.4b. is not applicable when entering MODE 1.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One steam supply to turbine driven AFW pump inoperable.
A.1 Restore steam supply to OPERABLE status.
7 days AND 10 days from discovery of failure to meet the LCO B.
One AFW train inoperable for reasons other than Condition A.
B.1 Restore AFW train to OPERABLE status.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> AND 10 days from discovery of failure to meet the LCO (continued)
Wolf Creek - Unit 1 3.7-15 Amendment No. 123, 155, 171, 177, 184
3.7.5 ACTIONS (continued)
CONDITION C.
Required Action and associated Completion Time for Condition A or B not met.
OR Two AFW trains inoperable.
D.
Three AFW trains inoperable.
AFW System REQUIRED ACTION C.1 Be in MODE 3.
AND C.2 Be in MODE 4.
D.1
NOTE------------
LCO 3.0.3 and all other LCO Required Actions requiring MODE changes are suspended until one AFW train is restored to OPERABLE status.
Initiate action to restore one AFW train to OPERABLE status.
COMPLETION TIME 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 12 hours Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.7.5.1
NOTE--------------------------------
l\\Iot required to be performed for the AFW flow control valves until the system is placed in standby or THERMAL POWER is > 10% RTP.
Verify each AFW manual, power operated, and automatic valve in each water flow path, and in both steam supply flow paths to the steam turbine driven pump, that is not locked, sealed, or otherwise secured in position, is in the correct position.
FREQUENCY 31 days (continued)
Wolf Creek - Unit 1 3.7-16 Amendment No. 123, 171, 177, 184
AFW System 3.7.5 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.7.5.2
NOTE--------------------------------
Not required to be performed for the turbine driven AFW pump until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after ~ 900 psig in the steam generator.
Verify the developed head of each AFW pump at the flow test point is greater than or equal to the required developed head.
In accordance with the Inservice Test Program SR 3.7.5.3 Verify each AFW automatic valve that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.
18 months SR 3.7.5.4
NOTE--------------------------------
Not required to be performed for the turbine driven AFW pump until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after ~ 900 psig in the steam generator.
Verify each AFW pump starts automatically on an actual or simulated actuation signal.
18 months SR 3.7.5.5 Verify proper alignment of the required AFW flow paths by verifying flow from the condensate storage tank to each steam generator.
Prior to entering MODE2 whenever unit has been in MODE 5 or 6 for> 30 days Wolf Creek - Unit 1 3.7-17 Amendment No. 123, 171, 177, 184 I
CST 3.7.6 3.7 PLANT SYSTEMS 3.7.6 Condensate Storage Tank (CST)
LCO 3.7.6 The CST contained water volume shall be ~ 281,000 gal.
APPLICABILITY:
MODES 1, 2, and 3.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
CST contained water volume not within limit.
A.1 AND A.2 Verify by administrative means OPERABILITY of backup water supply.
Restore CST contained water volume to within limit.
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> AND Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter 7 days B.
Required Action and associated Completion Time not met.
B.1 AND Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> B.2 Be in MODE 4.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Wolf Creek - Unit 1 3.7-18 Amendment No. 123, 171, 177, 184 I
CST 3.7.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.1 Verify the CST contained water volume is z 281,000 gal.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Wolf Creek - Unit 1 3.7-19 Amendment No. 123, 171, 177, 184 I
CCW System 3.7.7 3.7 PLANT SYSTEMS 3.7.7 Component Cooling Water (CCW) System LCO 3.7.7 Two CCW trains shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One CCW train inoperable.
A.1
N0 TE------------
Enter applicable Conditions and Required Actions of LCO 3.4.6, "RCS Loops - MODE 4,"
for residual heat removal loops made inoperable by CCW.
Restore CCW train to OPERABLE status.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> B.
Required Action and associated Completion Time of Condition A not met.
B.1 AND Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> B.2 Be in MODE 5.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Wolf Creek - Unit 1 3.7-20 Amendment No. 123, 171, 177, 184 I
CCW System 3.7.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.7.1
NOTE--------------------------------
Isolation of CCW flow to individual components does not render the CCW System inoperable.
Verify each CCW manual, power operated, and automatic valve in the flow path servicing safety related equipment, that is not locked, sealed, or otherwise secured in position, is in the correct position.
31 days SR 3.7.7.2 Verify each CCW automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.
18 months SR 3.7.7.3 Verify each CCW pump starts automatically on an actual or simulated actuation signal.
18 months Wolf Creek - Unit 1 3.7-21 Amendment No. 123, 171, 177, 184 I
ESW System 3.7.8 3.7 PLANT SYSTEMS 3.7.8 Essential Service Water (ESW) System LCO 3.7.8 Two ESW trains shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One ESW train inoperable.
A.1
NOTES-----------
- 1.
Enter applicable Conditions and Required Actions of LCO 3.8.1, "AC Sources - Operating,"
for emergency diesel generator made inoperable by ESW System.
- 2.
Enter applicable Conditions and Required Actions of LCO 3.4.6, "RCS Loops - MODE 4," for residual heat removal loops made inoperable by ESW System.
Restore ESW train to OPERABLE status.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (continued)
Wolf Creek - Unit 1 3.7-22 Amendment No. 123, 171,177, 184 I
ESW System 3.7.8 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B.
Required Action and associated Completion B.1 Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Time of Condition A not met.
AND B.2 Be in MODE 5.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.8.1
NOTE--------------------------------
Isolation of ESW System flow to individual components does not render the ESW System inoperable.
Verify each ESW manual, power operated, and automatic valve in the flow path servicing safety related equipment, that is not locked, sealed, or otherwise secured in position, is in the correct position.
31 days SR 3.7.8.2 Verify each ESW automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.
18 months SR 3.7.8.3 Verify each ESW pump starts automatically on an actual or simulated actuation signal.
18 months Wolf Creek - Unit 1 3.7-23 Amendment No. 123, 171, 177, 184 I
3.7.9 UHS 3.7 PLANT SYSTEMS 3.7.9 Ultimate Heat Sink (UHS)
LCO 3.7.9 The UHS shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Plant inlet water temperature of UHS not within limit.
A.1 AND A.2 Verify water level of main cooling lake :::=: 1075 ft.
mean sea level.
Verify plant inlet water temperature of UHS is 5 94°F.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter Once per hour B.
Required Action and associated Completion Time not met.
B.1 AND Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> OR UHS inoperable for reasons other than Condition A.
B.2 Be in MODE 5.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Wolf Creek - Unit 1 3.7-24 Amendment No. 123, 134, 171, 177, 184
3.7.9 UHS SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.9.1 Verify water level of UHS is ~ 1070 ft mean sea level.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> SR 3.7.9.2 Verify plant inlet water temperature of UHS is :s: 90°F.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Wolf Creek - Unit 1 3.7-25 Amendment No. 123, 134, 171, 177, 184
CREVS 3.7.10 3.7 PLANT SYSTEMS 3.7.10 Control Room Emergency Ventilation System (CREVS)
LCO 3.7.10 Two CREVS trains shall be OPERABLE.
NOTE---------------------------------------------
The control room envelope (CRE) and control building envelope (CBE) boundaries may be opened intermittently under administrative controls.
APPLICABILITY:
MODES 1, 2, 3, 4, 5, and 6, During movement of irradiated fuel assemblies.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One CREVS train inoperable for reasons other than Condition B.
A.1 Restore CREVS train to OPERABLE status.
7 days B.
One or more CREVS trains inoperable due to an inoperable CRE boundary or an inoperable CBE boundary in MODES 1, 2, 3,or4.
B.1 AND B.2 AND B.3 Initiate action to implement mitigating actions.
Verify mitigating actions to ensure CRE occupant radiological exposures will not exceed limits and CRE occupants are protected from chemical and smoke hazards.
Restore CRE boundary and CBE boundary to OPERABLE status.
Immediately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 90 days (continued)
Wolf Creek - Unit 1 3.7-26 Amendment No. 123, 134, 171, 177, 7-9, 184
3.7.10 ACTIONS (continued)
CONDITION C.
Required Action and associated Completion Time of Condition A or B not met in MODE 1, 2, 3, or4.
D.
Required Action and associated Completion Time of Condition A not met in MODE 5 or 6, or during movement of irradiated fuel assemblies.
E. Two CREVS trains inoperable in MODE 5 or 6, or during movement of irradiated fuel assemblies.
OR One or more CREVS trains inoperable due to an inoperable CRE boundary or an inoperable CBE boundary in MODE 5 or 6, or during movement of irradiated fuel assemblies.
Wolf Creek - Unit 1 CREVS REQUIRED ACTION COMPLETION TIME C.1 Be in MODE 3.
AND C.2 Be in MODE 5.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 36 hours D.1.1 Place OPERABLE CREVS train in CRVIS mode.
AND D.1.2 Verify OPERABLE CREVS train is capable of being powered by an emergency power source.
OR D.2.1 Suspend CORE ALTERATIONS.
AND D.2.2 Suspend movement of irradiated fuel assemblies.
Immediately Immediately Immediately Immediately E.1 Suspend CORE ALTERATIONS.
AND E.2 Suspend movement of irradiated fuel assemblies.
Immediately Immediately (continued) 3.7-27 Amendment No. 123, 131, 134, 171, 177, 179, 184
3.7.10 CREVS ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME F.
Two CREVS trains inoperable in MODE 1, 2, 3, or 4 for reasons other than Condition B.
F.1 Enter LCO 3.0.3.
Immediately SURVEILLANCE REQUIREMENTS SR 3.7.10.1 SURVEILLANCE Operate each CREVS train pressurization filter unit for ~ 10 continuous hours with the heaters operating and each CREVS train filtration filter unit for
~ 15 minutes.
FREQUENCY 31 days SR 3.7.10.2 Perform required CREVS filter testing in accordance with the Ventilation Filter Testing Program (VFTP).
In accordance with the VFTP SR 3.7.10.3 Verify each CREVS train actuates on an actual or simulated actuation signal.
18 months SR 3.7.10.4 Perform required unfiltered air inleakage testing of the CRE and CBE boundaries in accordance with the Control Room Envelope Habitability Program.
In accordance with the Control Room Habitability Program Wolf Creek - Unit 1 3.7-28 Amendment No. 123, 134, 171, 177, 4-79, 184
3.7.11 CRACS 3.7 PLANT SYSTEMS 3.7.11 Control Room Air Conditioning System (CRACS)
LCO 3.7.11 Two CRACS trains shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3, 4, 5, and 6, During movement of irradiated fuel assemblies.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One CRACS train inoperable.
A.1 Restore CRACS train to OPERABLE status.
30 days B.
Required Action and associated Completion Time of Condition A not met in MODE 1, 2, 3, or 4.
B.1 AND B.2 Be in MODE 3.
Be in MODE 5.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 36 hours (continued)
Wolf Creek - Unit 1 3.7-29 Amendment No. 123, 134, 171, 177, 184
3.7.11 ACTIONS (continued)
CONDITION C.
Required Action and associated Completion Time of Condition A not met in MODE 5 or 6, or during movement of irradiated fuel assemblies.
D.
Two CRACS trains inoperable in MODE 5 or 6, or during movement of irradiated fuel assemblies.
E.
Two CRACS trains inoperable in MODE 1, 2, 3,or4.
REQUIRED ACTION C.1.1 Place OPERABLE CRACS train in operation.
AND C.1.2 Verify OPERABLE CRACS train is capable of being powered by an emergency power source.
OR C.2.1 Suspend CORE ALTERATIONS.
AND C.2.2 Suspend movement of irradiated fuel assemblies.
D.1 Suspend CORE ALTERATIONS.
AND D.2 Suspend movement of irradiated fuel assemblies.
E.1 Enter LCO 3.0.3.
CRACS COMPLETION TIME Immediately Immediately Immediately Immediately Immediately Immediately Immediately Wolf Creek - Unit 1 3.7-30 Amendment No. 123, 134, 171, 177, 184
3.7.11 CRACS SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.11.1 Verify each CRACS train has the capability to remove 18 months the assumed heat load.
Wolf Creek - Unit 1 3.7-31 Amendment No. 123, 134, 171, 177, 184
3.7 PLANT SYSTEMS 3.7.12 Emergency Core Cooling System (ECCS) Pump Room Exhaust Air Cleanup System (PREACS)
NOT USED Wolf Creek - Unit 1 3.7-32 Amendment No. 123, 134, 171, 177, 184
EES 3.7.13 3.7 PLANT SYSTEMS 3.7.13 Emergency Exhaust System (EES)
LCO 3.7.13 APPLICABILITY:
ACTIONS Two EES trains shall be OPERABLE.
NOTE-----------------------------------------------
The auxiliary building or fuel building boundary may be opened intermittently under administrative controls.
MODES 1, 2, 3, and 4, During movement of irradiated fuel assemblies in the fuel building.
NOTE------------------------------------------------
The SIS mode of operation is required only in MODES 1, 2, 3, and 4. The FBVIS mode of operation is required only during movement of irradiated fuel assemblies in the fuel building.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One EES train inoperable in MODE 1,2,3, or4.
A.1 Restore EES train to OPERABLE status.
7 days B.
Two EES trains inoperable due to inoperable auxiliary building boundary in MODE 1, 2, 3, or4.
B.1 Restore auxiliary building boundary to OPERABLE status.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (continued)
Wolf Creek - Unit 1 3.7-33 Amendment No. 123, 132, 134, 171, 177, 184
3.7.13 ACTIONS (continued)
CONDITION C.
Required Action and associated Completion Time of Condition A or B not met in MODE 1, 2, 3, or4.
OR Two EES trains inoperable in MODE 1, 2, 3, or4 for reasons other than Condition B.
D.
One EES train inoperable during movement of irradiated fuel assemblies in the fuel building.
E.
Two EES trains inoperable due to inoperable fuel building boundary during movement of irradiated fuel assemblies in the fuel building.
REQUIRED ACTION C.1 Be in MODE 3.
AND C.2 Be in MODE 5.
D.1 Place OPERABLE EES train in operation in FBVIS mode.
OR D.2 Suspend movement of irradiated fuel assemblies in the fuel building.
E.1 Restore fuel building boundary to OPERABLE status.
EES COMPLETION TIME 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 36 hours Immediately Immediately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (continued)
Wolf Creek - Unit 1 3.7-34 Amendment No. 123, 132, 134, 171, 177, 184
3.7.13 EES ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME F.
Required Action and associated Completion Time of Condition E not met.
Two EES trains inoperable during movement of irradiated fuel assemblies in the fuel building for reasons other than Condition E.
F.1 Suspend movement of irradiated fuel assemblies in the fuel building.
Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.13.1 Operate each EES train for ~ 10 continuous hours with the heaters operating.
31 days SR 3.7.13.2 Perform required EES filter testing in accordance with the Ventilation Filter Testing Program (VFTP).
In accordance with the VFTP SR 3.7.13.3 Verify each EES train actuates on an actual or simulated actuation signal.
18 months (continued)
Wolf Creek - Unit 1 3.7-35 Amendment No. 123, 132, 134, 171, 177, 184
3.7.13 EES SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.7.13.4 Verify one EES train can maintain a negative pressure ~ 0.25 inches water gauge with respect to atmospheric pressure in the auxiliary building during the SIS mode of operation.
18 months on a STAGGERED TEST BASIS SR 3.7.13.5 Verify one EES train can maintain a negative pressure ~ 0.25 inches water gauge with respect to atmospheric pressure in the fuel building during the FBVIS mode of operation.
18 months on a STAGGERED TEST BASIS Wolf Creek - Unit 1 3.7-36 Amendment No. 123, 132, 134, 171, 177, 184
3.7 PLANT SYSTEMS 3.7.14 Penetration Room Exhaust Air Cleanup System (PREACS)
NOT USED Wolf Creek - Unit 1 3.7-37 Amendment No. 123, 134, 171, 177, 184
3.7.15 Fuel Storage Pool Water Level 3.7 PLANT SYSTEMS 3.7.15 Fuel Storage Pool Water Level LCO 3.7.15 The fuel storage pool water level shall be ~ 23 ft over the top of irradiated fuel assemblies seated in the storage racks.
APPLICABILITY:
During movement of irradiated fuel assemblies in the fuel storage pool.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A,
Fuel storage pool water level not within limit.
A,1
NOTE-------------
LCO 3.0.3 is not applicable.
Suspend movement of irradiated fuel assemblies in the fuel storage pool.
Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.15.1 Verify the fuel storage pool water level is ~ 23 ft 7 days above the top of the irradiated fuel assemblies seated in the storage racks.
Wolf Creek - Unit 1 3.7-38 Amendment No. 123, 134, 171, 177, 184
Fuel Storage Pool Boron Concentration 3.7.16 3.7 PLANT SYSTEMS 3.7.16 Fuel Storage Pool Boron Concentration LCO 3.7.16 The fuel storage pool boron concentration shall be ~ 2165 ppm.
APPLICABILITY:
When fuel assemblies are stored in the fuel storage pool and a fuel storage pool verification has not been performed since the last movement of fuel assemblies in the fuel storage pool.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Fuel storage pool boron concentration not within limit.
NOTE-------------------
LCO 3.0.3 is not applicable.
A.1 Suspend movement of fuel assemblies in the fuel storage pool.
Immediately AND A.2.1 Initiate action to restore fuel storage pool boron concentration to within limit.
Immediately OR A.2.2 Verify by administrative means that a non-Region 1 fuel storage pool verification has been performed since the last movement of fuel assemblies in the fuel storage pool.
Immediately Wolf Creek - Unit 1 3.7-39 Amendment No. 123, 134, 171, 177, 184
3.7.16 Fuel Storage Pool Boron Concentration SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.16.1 Verify the fuel storage pool boron concentration is 7 days within limit.
Wolf Creek - Unit 1 3.7-40 Amendment No. 123, 134, 171, 177, 184
3.7.17 Spent Fuel Assembly Storage 3.7 PLANT SYSTEMS 3.7.17 Spent Fuel Assembly Storage LCO 3.7.17 The combination of initial enrichment and burnup of each spent fuel assembly stored in Region 2 or 3 shall be within the Acceptable Domain of Figure 3.7.17-1 or in accordance with Specification 4.3.1.1.
APPLICABILITY:
Whenever any fuel assembly is stored in Region 2 or 3 of the fuel storage pool.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Requirements of the LCO not met.
A.1
NOTE-------------
LCO 3.0.3 is not applicable.
Initiate action to move the noncomplying fuel assembly to Region 1.
Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.7.17.1 Verify by administrative means the initial enrichment and burnup of the fuel assembly is in accordance with Figure 3.7.17-1 or Specification 4.3.1.1.
FREQUENCY Prior to storing the fuel assembly in Region 2 or 3 Wolf Creek - Unit 1 3.7-41 Amendment No. 123, 134, 171,177, 184
Ace,EPTAB B~~ NUP 0 )MAIN
/
FOR REGIOI 2 A D 3 SO ORAGE
~
r;.,v
/
'" /
0'+
~
/
~ /
/
(,~
V ~~ /'
/
~
/..~ V
~~/
/@ V "tov '/
V UNAC ::EPTAE LE aUI NUP t: OMAIN FOR
~EGION Z OR 3 STO ~AGE I
I 3.7.17 Spent Fuel Assembly Storage 55000 50000 40000 35000 30000 10000 15000 10000 saoo o
1.5 2.0 3.0
- s.s 4.0 5.0 FUEL ASSEMBLY INITIAL ENRICHMENT (w/o ~-235)
Figure 3.7.17-1 (page 1 of 1)
Minimum Required Fuel Assembly Burnup as a Function of Initial Enrichment to Permit Storage in Regions 2 and 3 Wolf Creek - Unit 1 3.7-42 Amendment No. 12a, 1a4, 171, 177, 184
Secondary Specific Activity 3.7.18 3.7 PLANT SYSTEMS 3.7.18 Secondary Specific Activity LCO 3.7.18 The specific activity of the secondary coolant shall be:5: 0.10 IlCi/gm DOSE EQUIVALENT 1-131.
APPLICABILITY:
MODES 1,2,3, and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Specific activity not within limit.
A.1 AND A.2 Be in MODE 3.
Be in MODE 5.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.18.1 Verify the specific activity of the secondary coolant is 31 days
- 5: 0.10 IlCi/gm DOSE EQUIVALENT 1-131.
Wolf Creek - Unit 1 3.7-43 Amendment No. 123, 134, 171, 177, 184
3.7.19 SSIVs 3.7 PLANT SYSTEMS 3.7.19 Secondary System Isolation Valves (SSIVs)
LCO 3.7.19 Each SSIV shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, and 3, except when the SSIV is closed and de-activated, or is closed and isolated by a closed manual valve, or the flow path is isolated by a combination of closed manual valve(s) and closed de activated automatic valve(s).
ACTIONS
NOTE--------------------------------------------------------------
- 1.
Separate Condition entry is allowed for each SSIV.
- 2.
SSIVs may be unisolated intermittently under administrative controls.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more SSIVs inoperable.
A.1 AND A.2 Close or isolate SSIV.
Verify SSIV is closed or isolated.
7 days Once per 7 days B.
Required Action and associated Completion Time not met.
8.1 AND B.2 Be in MODE 3.
Be in MODE 4.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 12 hours Wolf Creek - Unit 1 3.7-44 Amendment No. 184
3.7.19 SSIVs SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.19.1 Verify each automatic SSIV in the flow path is in the correct position.
31 days SR 3.7.19.2 Verify the isolation time of each automatic SSIV is within limit.
In accordance with the Inservice Testing Program SR 3.7.19.3 Verify each automatic SSIV in the flow path actuates to the isolation position on an actual or simulated actuation signal.
18 months Wolf Creek - Unit 1 3.7-45 Amendment No. 184
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 184 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-42 WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482
1.0 INTRODUCTION
By "ET 08-0039, Revision to TS 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, TS 3.7.2, [[system" contains a listed "[" character as part of the property label and has therefore been classified as invalid.s (Msivs), and Addition of New TS 3.7.19, Secondary System Isolation Valves|letter dated August 14, 2008]] (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082350068), and supplemented by letter dated April 10, 2009 (ADAMS Accession No. ML091100488), Wolf Creek Nuclear Operating Corporation (the licensee), submitted a request for changes to the Technical Specifications (TSs) for Wolf Creek Generating Station (WCGS). The changes would revise TS 3.7.2, "Main Steam Isolation Valves (MS/Vs)," and TS 3.3.2, "Engineered Safety Feature Actuation System (ESFAS)
Instrumentation." The change would also add new TS 3.7.19, "Secondary System Isolation Valves (SSIVs)."
The licensee's supplemental letter dated April 10, 2009, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the U.S. Nuclear Regulatory Commission (NRC) staff's original proposed no significant hazards consideration determination as published in the Federal Register on October 7,2008 (73 FR 58679).
2.0 REGULATORY EVALUATION
Title 10 of the Code of Federal Regulations (10 CFR), Section 50.36, "Technical specifications,"
contains the requirements for the content of TS. Pursuant to 10 CFR 50.36, TSs are required to include items in the following five specific categories related to station operation: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation (LCOs); (3) surveillance requirements (SRs); (4) design features; and (5) administrative controls.
Paragraph 50.36(c)(2)(ii) of 10 CFR lists the criteria used to determine whether or not LCOs must be established in TSs for items related to plant operation. If the item falls into one of the four categories below, an LCO must be established in the TSs to ensure the lowest functional capability or performance level of equipment required for safe operation of the facility will be met. The four criteria are:
- 2 Criterion 1 Installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary.
Criterion 2 A process variable, design feature, or operating restriction that is an initial condition of a design basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
Criterion 3 A structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
Criterion 4 An structure, system, or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety.
Section 50.36 of 10 CFR does not specify each particular requirement to be included in a plant's TSs, nor does it specify the format of a plant's TSs. Rather, the NRC publishes generic guidance on TS format and content. The NRC published a set of Standard Technical Specifications (STSs) in NUREG-1431, Revision 3, "Standard Technical Specifications, Westinghouse Plants," dated March 2004. The STSs are a guide to what a plant's TSs should contain with regard to format and content. The STSs are not requirements in a regulatory sense, but licensees adopting portions of the improved STSs to existing TSs should adopt all related requirements, as applicable, to achieve a high degree of standardization and consistency.
The NRC staff reviewed the proposed changes for compliance with 10 CFR 50.36 and agreement with the precedent as established in STSs. In general, licensees cannot justify TS changes solely on the basis of adopting the model STSs. To ensure this, the NRC staff makes a determination that proposed changes maintain adequate safety. Changes that result in relaxation (less restrictive condition) of current TS requirements require detailed justification.
Licensees may revise the TSs to adopt improved STS format and content provided that a plant specific review supports a finding of continued adequate safety because: (1) the change is editorial,. administrative or provides clarification (i.e., no requirements are materially altered);
(2) the change is more restrictive than the licensee's current requirement; or (3) the change is less restrictive than the licensee's current requirement, but nonetheless still affords adequate assurance of safety when judged against current regulatory standards. The detailed application of this general framework, and additional specialized guidance, are discussed in Section 3.0 of this safety evaluation in the context of specific proposed changes.
3.0 TECHNICAL EVALUATION
The MSIV bypass valves are air-operated, 2-inch bypass valves around the MSIVs. The bypass valves are provided for warming of downstream steam lines and equalizing the steam pressure across the MSIVs. The MSIV bypass valves are normally shut. If they are open when a
- 3 steamline isolation signal is generated, they are automatically shut to ensure isolation of steam flow from the secondary side of steam generators following a high-energy line break (HELB),
thereby mitigating a design-basis accident (DBA). Open MSIV bypass valves constitute a flow path similar to the MSIVs such that the MSIV bypass valves should be SUbject to the same or similar requirements as the MSIVs to ensure that assumptions in the safety analyses for DBAs remain valid.
The steam generator blowdown system is used to maintain the steam generator secondary side water chemistry within specifications. The blowdown system also provides the means to sample the secondary side of the steam generators, drain the steam generators during outages and re-circulate the steam generator water during wet layup conditions. The steam generator blowdown isolation valves (SGBIVs) and steam generator blowdown sample isolation valves (SGBSIVs) are installed to prevent uncontrolled blowdown from more than one steam generator, thereby mitigating a DBA. The SGBSIVs also isolate the non-safety-related portions from the safety-related portions of the system. Open SGBIVs and SGBSIVs could create the possibility of an unisolated secondary side following a HELB. The open valves may also prevent the required flow of auxiliary feedwater to the intact steam generators following a HELB.
Both of these situations invalidate the assumptions in the safety analyses for DBAs. Therefore, the SGBIVs and SGBSIVs should be subject to new TS requirements to ensure that assumptions in the safety analyses for DBAs remain valid.
The licensee submitted proposed changes to TS 3.3.2, "Engineered Safety Feature Actuation System (ESFAS) Instrumentation," and TS 3.7.2, "Main Steam Isolation Valves (MSIVs)." The licensee also proposed the addition of new TS 3.7.19, "Secondary System Isolation Valves (SSIVs)." The changes place requirements on the MSIV bypass valves, SGBIVs, and SGBSIVs to ensure that assumptions in the safety analyses for DBAs remain valid. Changes to the Table of Contents and TS Table 3.3.2-1 were also submitted to provide needed consistency due to the other changes.
The NRC staff reviewed the proposed TS changes to determine if the proposed TSs adequately meet the requirements of 10 CFR 50.36, and if the proposed TSs are consistent with WCGS's current licensing basis. The framework mentioned in the last paragraph of Section 2.0 was used to evaluate the proposed changes.
The NRC staff also compared the proposed TSs to the content of STSs. Differences between the content of the proposed TSs and the content of STSs are also addressed below in the applicable section. Minor differences between STSs and plant-specific TSs are expected since each plant has a unique licensing basis that may not be totally reflected in !\\IRC's generic guidance.
3.1 TS 3.7.2, "Main Steam Isolation Valves (MSIVs)"
The current TS 3.7.2 contains an LCO, applicability statement, and the associated conditions, required actions, completion times, and SRs for WCGS's MSIVs. The licensee proposed adding the MSIV Bypass Valves to the scope of the TS LCO and applicability statement. The licensee also proposed adding Conditions, Required Actions, Completion Times, and SRs related to the MSIV Bypass Valves to the TSs.
- 4 The LCO would be revised to state "Four MSIVs and their associated actuator trains, and four MSIV bypass valves shall be OPERABLE." The applicability statement would be modified by two Notes. Note 1 would state "All MSIV's and their associated actuator trains may be inoperable in MODES 2 and 3 when closed and de-activated." Note 2 would state "One or more MSIV bypass valves may be inoperable when closed and deactivated, closed and isolated by a closed manual valve, or isolated by two closed manual valves."
The licensee proposed replacing current Condition H with new Condition Hand re-Iettering current Conditions H and I as new Conditions I and J, respectively. The associated Required Actions and Completion Times of new Conditions I and J would be re-Iettered accordingly. The new Condition H would apply when one or more MSIV bypass valves are inoperable. The licensee would be required to close or isolate the affected MSIV bypass valve within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and verify the valve is closed or isolated once per 7 days. A Note will also be added to Condition H that states "Separate Condition entry is allowed for each MSIV bypass valve."
New Condition J would be modified to apply when the Required Action and Completion Times of either new Condition H or new Condition I are not met. The Required Actions and Completion Times of Condition J would not be changed.
The licensee proposed adding SR 3.7.2.3 and SR 3.7.2.4 to the SR portion of TS 3.7.2.
SR 3.7.2.3 requires the licensee to verify each MSIV bypass valve actuates to the isolation position on an actual or simulated actuation signal with a frequency of 18 months. SR 3.7.2.4 requires the licensee to verify that the isolation time of each MSIV bypass valve is within limit with a frequency that is in accordance with the Inservice Testing (1ST) Program.
The licensee also proposed editorial changes to the lettering of the TS Conditions and Required Actions to make the TS elements consistent.
The NRC staff reviewed the proposed changes to TS 3.7.2 and the licensee's justifications for the proposed changes. The NRC staff evaluated the proposed changes to TS 3.7.2 using the framework discussed at the end of Section 2.0 and the end of Section 3.0. The staff determined that the changes are more restrictive than current WCGS TS requirements, because the current WCGS TSs do not have requirements for MSIV bypass valves. The staff concluded that the changes are consistent with the WCGS licensing basis and meet the criteria for inclusion in TS.
The NRC staff also concluded that the new Required Action and Completion Times for the new Condition H are acceptable and consistent with similar Required Actions and Completion Times for MSIVs. Therefore, the staff concludes the proposed changes to TS 3.7.2 acceptable.
3.2 TS 3.3.2, "Engineered Safety Feature Actuation System (ESFAS) Instrumentation" The licensee proposed changing footnotes to Table 3.3.2-1 in TS 3.3.2. The changes reflect the addition of the MSIV bypass valves to TS 3.7.2. The licensee proposed changing footnote (i) from "Except when all MSIVs are closed" to "Except when all MSIVs are closed and de activated; and all MSIV bypass valves are closed and de-activated, or closed and isolated by a closed manual valve, or isolated by two closed manual valves." The licensee proposed adding new footnote (I), "Except when all MSIV's are closed and de-activated." The licensee also proposed changing the footnote reference for Function 4.c of Table 3.3.2-1 from (i) to (I).
- 5 The NRC staff reviewed the proposed changes to TS 3.3.2 and the licensee's justifications for the proposed changes. The NRC staff evaluated the proposed changes to TS 3.3.2 using the framework discussed at the end of Section 2.0 and the end of Section 3.0. The NRC staff concluded that the changes are editorial because they are necessary to ensure consistency with the changes made to TS 3.7.2. The NRC staff also concluded that the proposed footnote language is consistent with STSs. Therefore, the staff concludes the proposed changes to TS 3.3.2 are acceptable.
3.3 TS 3.7.19. "Secondary System Isolation Valves (SSIVs)"
The licensee proposed adding TS 3.7.19. The LCO and applicability statements for TS 3.7.19 would require each SSIV and SGBSIV to be operable in MODES 1, 2, and 3, except when an SSIV is closed and de-activated, or is closed and isolated by a closed manual valve, or the flow path is isolated by a combination of closed manual valve(s) and closed de-activated automatic valve(s).
The actions section of proposed TS 3.7.19 contains Condition A and Condition B. Condition A would apply when one or more SSIVs are inoperable. Required Actions A.1 and A.2 require the licensee to close or isolate the inoperable SSIV(s) within 7 days and verify the inoperable SSIV(s) is/are closed or isolated once per 7 days. Condition B would apply when the Required Actions and associated Completion Times of Condition A are not met. Required Actions B.1 and 8.2 require the licensee to place the plant in MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and MODE 4 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, respectively. The Actions section contains two notes. Note 1 states that "Separate Condition entry is allowed for each SSIV." Note 2 states that "SSIVs may be unisolated intermittently under administrative controls."
The NRC staff reviewed the proposed new TS 3.7.19 and the licensee's justifications for the proposed changes. The NRC staff evaluated the proposed TS using the framework discussed at the end of Section 2.0 and the end of Section 3.0. The NRC staff determined that the LCO and applicability statements and notes for the actions section are acceptable because they meet the requirements of 10 CFR 50.36(c)(2). The NRC staff also noted that the LCO and applicability statements and notes for the Actions section are consistent with TS sections for equipment with similar safety functions, such as main feedwater regulating valves (MFRVs) and MFRV bypass valves. In a letter dated March 12, 2009 (ADAMS Accession No. N1L090620129),
the NRC staff requested additional justification for the 7-day completion time of Required Action A.1, since required action and completion times for valves with apparently similar safety functions, such as MFRVs and MFRV bypass valves, are 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The licensee provided their technical basis for the 7-day completion time by letter dated April 10,2009. In that letter, the licensee stated that a failure of an MFRV or N1FRV bypass valve has the potential to have a more significant effect on a main steam line break than a failure of an SGBIV or SGBSIV due to the difference in sizes of the piping and tubing for the respective lines. The piping associated with the MFRVs is 14 inches and the tubing associated with the SGBIV and SGBSIV is 3/8 inches. The licensee also stated that failure of an SGBIV has a negligible impact on the plant risk. The NRC staff reviewed the justification for the 7-day completion time and concluded that it provided an acceptable basis for the proposed 7-day completion time.
The SR section of proposed TS 3.7.19 contains three SRs. SR 3.7.19.1 requires the licensee to verify each automatic SSIV in the flow path is in the correct position every 31 days. SR 3.7.19.2
- 6 requires the licensee to verify the isolation time of each automatic SSIV is within limits and on a frequency specified in the 1ST Program. SR 3.7.19.3 requires the licensee to verify each automatic SSIV in the flow path actuates to the isolation position on an actual or simulated actuation signal every 18 months.
The NRC staff compared the SRs of the proposed new TS 3.7.19 to the requirements for SRs found in 10 CFR 50.36(c)(3). The NRC staff concluded that the SRs will assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LCO will be met. Therefore, the NRC staff concludes that the SRs are acceptable.
The NRC staff concludes that the proposed changes listed in Section 3.0 meet the regulatory requirements specified in Section 2.0 of this safety evaluation. The proposed changes to TS 3.7.2 are more restrictive than the current WCGS TS requirements. The changes to TS 3.3.2 are editorial in nature, and addition of TS 3.7.19 will support continued safe operation of WCGS.
In addition, the proposed changes will provide adequate assurance that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LCOs for the SGBIVs, SSIVs, and SGBSIVs will be met consistent with the requirements of 10 CFR 50.36. Therefore, the NRC staff concludes that the requested TS changes described in Section 3.0 are acceptable.
4.0 REGULATORY COMMITMENT In its "ET 08-0039, Revision to TS 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, TS 3.7.2, [[system" contains a listed "[" character as part of the property label and has therefore been classified as invalid.s (Msivs), and Addition of New TS 3.7.19, Secondary System Isolation Valves|letter dated August 14, 2008]], the licensee made a regulatory commitment to implement the proposed amendment prior to startup from Refueling Outage 17. The NRC staff concludes that this commitment is acceptable.
5.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Kansas State official was notified of the proposed issuance of the amendment. The State official had no comments.
6.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding published in the Federal Register on October 7, 2008 (73 FR 58679). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
- 7
7.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: Matthew E. Hamm Date: Jul y 31, 2009
- SE memo dated 5/29/09 OFFICE NRR/LPL4/PM NRR/LPL4/LA DIRS/ITSB/BC DSS/SRXB/BC DSS/SBPB/BC NAME BSingal JBurkhardt RElliott*
GCranston GCasto DATE 7/1/09 6/29/09 5/29/09 7/2109 7/6/09 OFFICE DE/EICB/BC OGC NRR/LPL4/BC NRR/LPL4/PM NAME WKemper HCA for LSubin MMarkley BSingal DATE 7/27109 7/20109 7/31/09 7/31/09