ML020810638
| ML020810638 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  (DPR-062, DPR-071, NPF-037, NPF-066) |
| Issue date: | 03/19/2002 |
| From: | Hansen A NRC/NRR/DLPM/LPD2 |
| To: | Keenan J Carolina Power & Light Co |
| References | |
| TAC MB3347, TAC MB3348 | |
| Download: ML020810638 (6) | |
Text
Control Rod Scram 3.1 REACTIVITY CONTROL SYSTEMS 3.1.4 Control Rod Scram Times LCO
3.1.4 APPLICABILITY
- a.
No more than 10 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.
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 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 Prior to within the limits of Table 3.1.4-1 with exceeding reactor steam dome pressure 2 800 psig.
40% RTP after each reactor shutdown 2 120 days (continued)
Amendment No. 219 I
Times 3.1.4 3.1-12 Brunswick Unit 1
Control Rod Scram Times 3.1.4 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.1.4.2 Verify, for a representative sample, each 120 days tested control rod scram time is within the cumulative limits of Table 3.1.4-1 with reactor steam operation in dome pressure z 800 psig.
MODE 1 SR 3.1.4.3 Verify each affected control rod scram time Prior to is within the limits of Table 3.1.4-1 with declaring any reactor steam dome pressure.
control rod OPERABLE after work on control rod or CRD System that could affect scram time SR 3.1.4.4 Verify each affected control rod scram time Prior to is within the limits of Table 3.1.4-1 with exceeding 40%
reactor steam dome pressure
- 800 psig.
RTP after fuel movement within the affected core cell AND Prior to exceeding 40% RTP after work on control rod or CRD System that could affect scram time Amendment No. 219 I
Brunswick Unit I 3.1-13
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.10 Technical Specifications (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.
- a.
Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.
- b.
Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following:
- 1.
A change in the TS incorporated in the license; or
- 2.
A change to the updated FSAR or Bases that requires NRC I
approval pursuant to 10 CFR 50.59.
- c.
The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the UFSAR.
- d.
Proposed changes that meet the criteria of Specification 5.5.10.b.1 or 5.5.10.b.2 above shall be reviewed and approved by the NRC prior to implementation.
Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).
5.5.11 Safety Function Determination Program (SFDP)
This program ensures loss of safety function is detected and appropriate actions taken.
Upon entry into LCO 3.0.6, an evaluation shall be made to determine if loss of safety function exists.
Additionally, other appropriate limitations and remedial or compensatory actions may be identified to be taken as a result of the support system inoperability and corresponding exception to entering supported system Condition and Required Actions.
This program implements the requirements of LCO 3.0.6.
- a.
The SFDP shall contain the following:
- 1.
Provisions for cross division checks to ensure a loss of the capability to perform the safety function assumed in the accident analysis does not go undetected; (continued)
Amendment No. 219 I Brunswick Unit 1 5.0-14
Control Rod Scram Times 3.1.4 3.1 REACTIVITY CONTROL SYSTEMS 3.1.4 Control Rod Scram Times LCO
3.1.4 APPLICABILITY
- a.
No more than 10 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 Rslow" shall occupy adjacent locations.
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 I
NOTE-----------------------
During single control rod scram time Surveillances, the control rod drive (CRD) pumps shall be isolated from the associated scram accumulator.
-i-i----------------------------------------------------
SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify each control rod scram time is Prior to within the limits of Table 3.1.4-1 with exceeding reactor steam dome pressure ? 800 psig.
40% RTP after each reactor shutdown S120 days (continued)
Amendment No. 245 I
Brunswick Unit 2 3.1-12
Control Rod Scram Times 3.1.4 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.1.4.2 Verify, for a representative sample, each 120 days tested control rod scram time is within the cumulative limits of Table 3.1.4-1 with reactor steam operation in dome pressure 2 800 psig.
MODE 1 SR 3.1.4.3 Verify each affected control rod scram time Prior to is within the limits of Table 3.1.4-1 with declaring any reactor steam dome pressure.
control rod OPERABLE after work on control rod or CRD System that could affect scram time SR 3.1.4.4 Verify each affected control rod scram time Prior to is within the limits of Table 3.1.4-1 with exceeding 40%
reactor steam dome pressure 800 psig.
RTP after fuel movement within the affected core cell AND Prior to exceeding 40% RTP after work on control rod or CRD System that could affect scram time Amendment No. 245 I
Brunswick Unit 2 3.1-13
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.10 Technical Specifications (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.
- a.
Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.
- b.
Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following:
- 1.
A change in the TS incorporated in the license; or
- 2.
A change to the updated FSAR or Bases that requires NRC approval pursuant to 10 CFR 50.5g.
- c.
The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the UFSAR.
- d.
Proposed changes that meet the criteria of Specification 5.5.10.b.1 or 5.5.10.b.2 above shall be reviewed and approved by the NRC prior to Implementation.
Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).
5.5.11 Safety Function Determination Program (SFDP)
This program ensures loss of safety function is detected and appropriate actions taken.
Upon entry into LCO 3.0.6, an evaluation shall be made to determine if loss of safety function exists.
Additionally, other appropriate limitations and remedial or compensatory actions may be identified to be taken as a result of the support system inoperability and corresponding exception to entering supported system Condition and Required Actions.
This program implements the requirements of LCO 3.0.6.
- a.
The SFDP shall contain the following:
- 1. Provisions for cross division checks to ensure a loss of the capability to perform the safety function assumed in the accident analysis does not go undetected; (continued)
Amendment No. 245 I
Brunswick Unit 2 5.0-14