ML062610190
| ML062610190 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 09/12/2006 |
| From: | NRC/NRR/ADRO/DORL/LPLI-1 |
| To: | |
| References | |
| TAC MD0013, TAC MD0014 | |
| Download: ML062610190 (1) | |
Text
(4)
PPL Susquehanna, LLC, 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 (5).
PPL Susquehanna, LLC, 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 license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level PPL Susquehanna, LLC is authorized to operate the facility at reactor core power levels not in excess of 3489 megawatts thermal in accordance with the conditions specified herein and in Attachment 1 to this license. The preoperational tests, startup tests and other items identified in Attachment 1 to this license shall be completed as specified. Attachment 1 is hereby incorporated into this license.
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 237, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. PPL Susquehanna, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
For Surveillance Requirements (SRs) that are new in Amendment 178 to Facility Operating License No.. NPF-14, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 178. For SRs that existed prior to Amendment 178, including SRs with modified acceptance, criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 178.
(3)
Conduct of Work Activities During Fuel Load and Initial Startup The operating licensee shall review by committee all facility construction, Preoperational Testing, and System Demonstration activities performed concurrently with facility initial fuel loading or with the facility Startup Test Amendment No. 5, +49, 47-8, +80, +88, +94, 2e5, -36, 237
PPL Rev. 1 Control Rod Scram Times 3.1.4 3.1 REACTIVITY CONTROL SYSTEMS 3.1.4 Control Rod Scram Times LCO 3.1.4
- a.
No more than 13 OPERABLE control rods shall be "slow," in accordance with Table 3.1.4-1; and
- b.
No more than 2 OPERABLE control rods that are "slow" shall occupy adjacent locations.
APPLICABILITY:
MODES 1 and 2.
- ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the LCO A.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 /> not met.
SURVEILLANCE REQUIREMENTS NOTE ---------------------------.............................
During single control rod scram time Surveillances, the control rod drive (CRD) pumps shall be isolated from the associated scram accumulator.
SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify each control rod scram time is within the Prior to exceeding 40% RTP limits of Table 3.1.4-1 with reactor steam dome after each reactor shutdown pressure >_ 800 psig.
> 120 days (continued)
SUSQUEHANNA - UNIT 1 TS / 3.1-12
.Amendment 1;76, 237
PPL Rev. 1 Control Rod Scram Times 3.1.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.4.2 Verify, for a representative sample, each tested 120 days cumulative control rod scram time is within the limits of operation in MODE 1 Table 3.1.4-1 with reactor steam dome pressure
_ 800 psig.
S RPrior to declaring control rod SR 3.1.4.3 Verify each affected control rod scram time is OPERABLE after work on within the limits of Table 3.1.4-1 with any reactor control rod or CRD System steam dome pressure.
that could affect scram time SR 3.1.4.4 Verify each affected control rod scram time is Prior to exceeding 40% RTP within the limits of Table 3.1.4-1 with reactor after fuel movement within steam dome pressure *_ 800 psig.
the affected core cell AND Prior to exceeding 40% RTP after work on control rod or CRD System that could affect scram time SUSQUEHANNA - UNIT 1 TS / 3.1-13 Amendment 1.78., 237 (4)
PPL Susquehanna, LLC, 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 (5)
PPL Susquehanna, LLC, 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 license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level PPL Susquehanna, LLC is authorized to operate the facility at reactor core power levels not in excess of 3489 megawatts thermal (100% power) in accordance with the conditions specified herein and in Attachment 1 to this license. The preoperational tests, startup tests and other items identified in to this license shall be completed as specified. Attachment 1 is hereby incorporated into this license.
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 214, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. PPL Susquehanna, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
For Surveillance Requirements (SRs) that are new in Amendment 151 to Facility Operating License No. NPF-22, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 151. For SRs that existed prior to Amendment 151, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 151.
2.C.(3)
PPL Susquehanna, LLC shall implement and maintain in effect all provisions of the approved fire protection program as described in the Fire Protection Review Report for the facility and as approved in Fire Protection Program, Section 9.5, SER, SSER#1, SSER#2, SSER#3, SSER#4, SSER#6, Safety Evaluation of Fire Protection Report dated August 9, 1989, Safety Evaluation Amendment No. +, e, +e3, +5e, 4-1-5, 4-53, +62, +69, 2-+2, 2+3, 214
PPL Rev. 1 Control Rod Scram Times 3.1.4 3.1 REACTIVITY CONTROL SYSTEMS Control Rod Scram Times 3.1.4 LCO 3.1.4
- a.
No more than 13 OPERABLE control rods shall be "slow," in accordance with Table 3.1.4-1; and
- b.
No more than 2 OPERABLE control rods that are "slow" shall occupy adjacent locations.
APPLICABILITY:
MODES 1 AND 2.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Requirements of the A.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 /> LCO not met.
SURVEILLANCE REQUIREMENTS L ~~IY
\\jI JJ During single control rod scram time Surveillances, the control rod drive (CRD) pumps shall be isolated from the associated scram accumulator.
SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify each control rod scram time is within the Prior to exceeding 40% RTP limits of Table 3.1.4-1 with reactor steam dome after each reactor shutdown pressure > 800 psig.
> 120 days (continued)
SUSQUEHANNA - UNIT 2 TS / 3.1-12 Amendment 1&1, 214
PPL Rev. 1 Control Rod Scram Times 3.1.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.4.2 Verify, for a representative sample, each tested 120 days cumulative control rod scram time is within the limits of operation in MODE 1 Table 3.1.4-1 with reactor steam dome pressure
> 800 psig.
SR 3.1.4.3 Verify each affected control rod scram time is Prior to declaring control rod within the limits of Table 3.1.4-1 with any reactor OPERABLE after work on steam dome pressure.
control rod or CRD System that could affect scram time SR 3.1.4.4 Verify each affected control rod scram time is Prior to exceeding 40% RTP within the limits of Table 3.1.4-1 with reactor after fuel movement within steam dome pressure > 800 psig.
the affected core cell AND Prior to exceeding 40% RTP after work on control rod or CRD System that could affect scram time SUSQUEHANNA - UNIT 2 TS / 3.1-13 Amendment IZ1, 214