BSEP 05-0109, Submittal of Technical Specification Bases Revisions

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Submittal of Technical Specification Bases Revisions
ML052350280
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 08/16/2005
From: O'Neil E
Progress Energy Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BSEP 05-0109
Download: ML052350280 (22)
v • d • e


Text

2j Progress Energy August 16, 2005 /

SERIAL: BSEP 05-0109 U. S. Nuclear Regulatory 4 ommission ATTN: Document Control}Desk Washington, DC 20555-0 01 l

Subject:

Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Docket Nos. 50-325 and 50-324/License Nos. DPR-71 and DPR-62 Submittal rf Technical Specification Bases Revisions Ladies and Gentlemen:

In accordance with Technical Specification (TS) 5.5.10 for the Brunswick Steam Electric Plant (BSEP), Unit Nos. 1 and 2, Carolina Power & Light Company, now doing business as Progress Energy Carolinas, Inc., is submitting Revisions 42 and 43 to the BSEP, Unit 1 TS Bases and Revisions 40 and 41 to the BSEP, Unit 2 TS Bases.

Please refer any questions regarding this submittal to Mr. Leonard R. Beller, Supervisor -

Licensing/Regulatory Programs, at (910) 457-2073.

Sincerely, Edward T. O'Neil Manager - Support Services Brunswick Steam Electric Plant WRM/wrm

Enclosures:

1. Summary of Revisions to Technical Specification Bases
2. Page Replacement Instructions
3. Unit 1 Technical Specification Bases Replacement Pages
4. Unit 2 Technical Specification Bases Replacement Pages Progress Energy Carolinas. Inc.

Brunswick Nuclear Plant P.O.Box 10429 Southport, NC 28461

Document Control Desk BSEP 05-0109 / Page 2 cc (with enclosures):

U. S. Nuclear Regulatory Commission, Region II ATTN: Dr. William D. Travers, Regional Administrator Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-8931 U. S. Nuclear Regulatory Commission ATTN: Mr. Eugene M. DiPaolo, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission (Electronic Copy Only)

ATTN: Ms. Brenda L. Mozafari (Mail Stop OWFN 8G9) 11555 Rockville Pike Rockville, MD 20852-2738 Ms. Jo A. Sanford Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510 Ms. Beverly 0. Hall, Section Chief Radiation Protection Section, Division of Environmental Health North Carolina Department of Environment and Natural Resources 3825 Barrett Drive Raleigh, NC 27609-7221

BSEP 05-0109 Enclosure 1 Page 1 of 1 Summary of Revisions to Technical Specification Bases Revision' Affected Date Implemented Title/Description Unit 42 1 July 28, 2005

Title:

Technical Specification Improvement to 40 2 Revise Control Rod Scram Time Testing Frequency

Description:

Revision 42 for Unit 1 and 40 for Unit 2 incorporated changes to Section 3.1.4 of the TS Bases associated with License Amendments 236 for Unit 1 and Amendment 264 for Unit 2, issued on May 31, 2005. These amendments modified the Unit 1 and Unit 2 TS requirements to adopt the provisions of TSTF-460.

43 1 August 9, 2005

Title:

Revised Actions for Reactor Coolant 41 2 System Leakage Detection Instrumentation

Description:

Revision 43 for Unit 1 and 41 for Unit 2 incorporated changes to Section 3.4.5 of the TS Bases associated with Amendment 237 for Unit 1 and Amendment 265 for Unit 2, issued on June 28, 2005. These amendments replaced the requirement of TS 3.4.5, Required Action D.1, to enter Limiting Condition for Operation 3.0.3 if required leakage detection systems are inoperable with the requirement to be in Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and Mode 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

I Revision 42 for Unit 1 and Revision 40 for Unit 2 incorporated change package TSC-2003-04.

Revision 43 for Unit 1 and Revision 41 for Unit 2 incorporated change package TSC-2005-03.

BSEP 05-0109 Enclosure 2 Page 1 of 1 Page Replacement Instructions - Unit 1 Remove I Insert Unit 1 - Bases Book 1 Title Page, Revision 41 Title Page, Revision 43 LOEP-1, Revision 41 LOEP-1, Revision 43 Table of Contents page i, Revision 31 Table of Contents page i, Revision 42 B 3.1.4-5, Revision 31 B 3.1.4-5, Revision 42 Unit 1 - Bases Book 2 LOEP-1, Revision 41 LOEP-1, Revision 43 B 3.4.5-3, Revision 41 B 3.4.5-3, Revision 43 Page ReplacementVInstructions - Unit 2 Remove Insert Unit 2 - BasesjBook 1 Title-Page, Revision 39 Title Page, Revision 41 LOEP-1, Revision 39 LOEP-1, Revision 41 Table of Contents page i, Revision 30 Table of Contents page i, Revision 40 B 3.1.4-5, Revision 30 B 3.1.4-5, Revision 40 Unit 2- Bases Book 2 LOEP-1, Revision 39 LOEP-1, Revision 41 B 3.4.5-3, Revision 39 B 3.4.5-3, Revision 41

BSEP 05-0109 Enclosure 3 Unit 1 Technical Specification Bases Replacement Pages

Unit 1 - Bases Book 1 Replacement Pages

BASES TO THE FACILITY OPERATING LICENSE DPR-71 TECHNICAL SPECIFICATIONS FOR BRUNSWICK STEAM ELECTRIC PLANT UNIT 1 CAROLINA POWER & LIGHT COMPANY REVISION 43

LIST OF EFFECTIVE PAGES - BASES Page No. Revision No. Page No. Revision No.

Title Page 43 B 3.1.1-6 31 B 3.1.2-1 31 List of Effective Pages - Book 1 B 3.1.2-2 31 B 3.1.2-3 31 LOEP-1 43 B 3.1.2-4 31 LOEP-2 36 B 3.1.2-5 31 LOEP-3 41 B 3.1.3-1 31 LOEP-4 36 B 3.1.3-2 31 B 3.1.3-3 31 i 42 B 3.1.3-4 31 ii 31 B 3.1.3-5 31 B 3.1.3-6 31 B 2.1.1-1 31 B 3.1.3-7 31 B 2.1.1-2 31 B 3.1.3-8 31 B 2.1.1-3 31 B 3.1.3-9 31 B 2.1.1-4 31 B 3.1.4-1 31 B 2.1.1-5 31 B 3.1.4-2 31 B 2.1.2-1 31 B 3.1.4-3 31 B 2.1.2-2 31 B 3.1.4-4 31 B 2.1.2-3 31 B 3.1.4-5 42 B 3.1.4-6 31 B 3.0-1 31 B 3.1.4-7 31 B 3.0-2 31 B 3.1.5-1 31 B 3.0-3 31 B 3.1.5-2 31 B 3.0-4 31 B 3.1.5-3 31 B 3.0-5 41 B 3.1.5-4 31 B 3.0-6 41 B 3.1.5-5 31 B 3.0-7 41 B 3.1.6-1 31 B 3.0-8 41 B 3.1.6-2 31 B 3.0-9 41 B 3.1.6-3 31 B 3.0-10 41 B 3.1.6-4 31 B 3.0-11 41 B 3.1.6-5 31 B 3.0-12 41 B 3.1.7-1 34 B 3.0-13 41 B 3.1.7-2 31 B 3.0-14 41 B 3.1.7-3 31 B 3.0-15 41 B 3.1.7-4 31 B 3.0-16 41 B 3.1.7-5 31 B 3.0-17 41 B 3.1.7-6 34 B 3.1.8-1 31 B 3.1.1-1 31 B 3.1.8-2 37 B 3.1.1-2 31 B 3.1.8-3 37 B 3.1.1-3 31 B 3.1.8-4 31 B 3.1.1-4 31 B 3.1.8-5 31 B 3.1.1-5 31 (continued)

Brunswick Unit 1 LOEP-1 Revision 43 l

TABLE OF CONTENTS B 2.0 SAFETY LIMITS (SLs)............................................................................... B 2.1.1-1 B 2.1.1 Reactor Core SLs .................................................... B 2.1.1-1 B 2.1.2 Reactor Coolant System (RCS) Pressure SL ....................................... B 2.1.2-1 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY ........... B 3.0-1 B 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY .......................... B 3.0-11 B 3.1 REACTIVITY CONTROL SYSTEMS .................................................... B 3.1.1-1 B 3.1.1 SHUTDOWN MARGIN (SDM).............................................................. B 3.1.1-1 B 3.1.2 Reactivity Anomalies .................................................... B 3.1.2-1 B 3.1.3 Control Rod OPERABILITY .................................................... B 3.1.3-1 B 3.1.4 Control Rod Scram Times .................................................... B 3.1.4-1 B 3.1.5 Control Rod Scram Accumulators .................................................... B 3.1.5-1 B 3.1.6 Rod Pattern Control .................................................... B 3.1.6-1 B 3.1.7 Standby Liquid Control (SLC) System.................................................. B 3.1.7-1 B 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves ...................... B 3.1.8-1 B 3.2 POWER DISTRIBUTION LIMITS...............................................................

.B 3.2.1-1 B 3.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)...................................................................................... B 3.2.1-1 B 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR) .................................... B 3.2.2-1 B 3.3 INSTRUMENTATION ......................................... B 3.3.1.1-1 B 3.3.1.1 Reactor Protection System (RPS) Instrumentation ............................... B 3.3.1.1-1 B 3.3.1.2 Source Range Monitor (SRM) Instrumentation ..................................... B 3.3.1.2-1 B 3.3.2.1 Control Rod Block Instrumentation ......................................... B 3.3.2.1-1 B 3.3.2.2 Feedwater and Main Turbine High Water Level Trip Instrumentation ..................................... B 3.3.2.2-1 B 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation ................................. B 3.3.3.1-1 B 3.3.3.2 Remote Shutdown Monitoring Instrumentation ..................................... B 3.3.3.2-1 B 3.3.4.1 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation......................................................... B 3.3.4.1-1 B 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation .................. B 3.3.5.1-1 B 3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation ........... B 3.3.5.2-1 B 3.3.6.1 Primary Containment Isolation Instrumentation .................................... B 3.3.6.1-1 B 3.3.6.2 Secondary Containment Isolation Instrumentation ................. .............. B 3.3.6.2-1 B 3.3.7.1 Control Room Emergency Ventilation (CREV) System Instrumentation ...... B 3.3.7.1-1 (continued)

Brunswick Unit 1 Revision No. 42 l

Control Rod Scram Times B 3.1.4 BASES SURVEILLANCE SR 3.1.4.2 REQUIREMENTS (continued) Additional testing of a sample of control rods is required to verify the continued performance of the scram function during the cycle. A representative sample contains at least 10% of the control rods. The sample remains representative if no more than 7.5% of the control rods in the sample tested are determined to be "slow." With more than 7.5% of I the sample declared to be "slow" per the criteria in Table 3.1.4-1, additional control rods are tested until this 7.5% criterion (i.e., 7.5% of the I entire sample size) is satisfied, or until the total number of "slow" control rods (throughout the core, from all surveillances) exceeds the LCO limit.

For planned testing, the control rods selected for the sample should be different for each test. This test is performed for each control rod in the sample from its fully withdrawn position. Data from inadvertent scrams should be used whenever possible to avoid unnecessary testing at power, even if the control rods with data may have been previously tested in a sample. The 200 day Frequency is based on operating experience that I has shown control rod scram times do not significantly change over an operating cycle. This Frequency is also reasonable based on the additional Surveillances done on the CRDs at more frequent intervals in accordance with LCO 3.1.3 and LCO 3.1.5, "Control Rod Scram Accumulators."

SR 3.1.4.3 When work that could affect the scram insertion time is performed on a control rod or the CRD System, testing must be done to demonstrate that each affected control rod retains adequate scram performance over the range of applicable reactor pressures from zero to the maximum permissible pressure. The scram testing must be performed once before declaring the control rod OPERABLE. The required scram time testing must demonstrate the affected control rod is still within acceptable limits.

This test is performed for each affected control rod from its fully withdrawn position. In lieu of actually initiating a scram for each affected control rod, testing that adequately demonstrates the scram times are within acceptable limits is allowed to satisfy this SR. The test may include any series of sequential, overlapping, or total steps so the entire scram (continued)

Brunswick Unit 1 B 3.1.4-5 Revision No. 42 l

Unit 1 - Bases Book 2 Replacement Pages

LIST OF EFFECTIVE PAGES - BASES Paae No. Revision No. Paae No. Revision No.

List of Effective Pages - Book 2 B 3.4.7-5 41 B 3.4.8-1 31 LOEP-1 43 B 3.4.8-2 31 I LOEP-2 41 B 3.4.8-3 31 LOEP-3 41 B 3.4.8-4 31 LOEP-4 31 B 3.4.8-5 31 LOEP-5 31 B 3.4.9-1 31 B 3.4.9-2 38 31 B 3.4.9-3 38 ii 31 B 3.4.9-4 31 B 3.4.9-5 38 B 3.4.1-1 31 B 3.4.9-6 38 B 3.4.1-2 31 B 3.4.9-7 31 B 3.4.1-3 31 B 3.4.9-8 31 B 3.4.1-4 31 B 3.4.9-9 38 B 3.4.1-5 31 B 3.4.10-1 31 B 3.4.1-6 31 B 3.4.10-2 31 B 3.4.2-1 31 B 3.4.2-2 31 B 3.5.1-1 31 B 3.4.2-3 31 B 3.5.1-2 31 B 3.4.2-4 31 B 3.5.1-3 31 B 3.4.3-1 31 B 3.5.1-4 36 B 3.4.3-2 31 B 3.5.1-5 36 B 3.4.3-3 31 B 3.5.1-6 41 B 3.4.3-4 31 B 3.5.1-7 31 B 3.4.4-1 31 B 3.5.1-8 31 B 3.4.4-2 31 B 3.5.1-9 31 B 3.4.4-3 31 B 3.5.1-10 31 B 3.4.4-4 31 B 3.5.1-11 31 B 3.4.4-5 31 B 3.5.1-12 31 B 3.4.5-1 31 B 3.5.1-13 31 B 3.4.5-2 31 B 3.5.1-14 31 B 3.4.5-3 43 B 3.5.1-15 31 I B 3.4.5-4 41 B 3.5.1-16 31 B 3.4.6-1 41 B 3.5.1-17 31 B 3.4.6-2 41 B 3.5.2-1 31 B 3.4.6-3 41 B 3.5.2-2 31 B 3.4.7-1 31 B 3.5.2-3 31 B 3.4.7-2 31 B 3.5.2-4 31 B 3.4.7-3 41 B 3.5.2-5 31 B 3.4.7-4 41 B 3.5.2-6 31 B 3.5.3-1 31 B 3.5.3-2 41 (continued)

Brunswick Unit 1 LOEP-1 Revision 43 l

RCS Leakage Detection Instrumentation B 3.4.5 BASES (continued)

APPLICABILITY In MODES 1, 2, and 3, leakage detection systems are required to be OPERABLE to support LCO 3.4.4. This Applicability is consistent with that for LCO 3.4.4.

ACTIONS A.1 With the drywell floor drain sump flow monitoring system inoperable, no other required instrumentation can provide the equivalent information to quantify LEAKAGE. However, the primary containment atmosphere radioactivity monitor will provide indication of changes in LEAKAGE.

With the drywell floor drain sump flow monitoring system inoperable, but with RCS unidentified and total LEAKAGE being determined every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (SR 3.4.4.1), operation may continue for 30 days. The 30 day Completion Time of Required Action A.1 is acceptable, based on operating experience, considering the multiple forms of leakage detection that are still available.

B.1 and B.2 With both gaseous and particulate primary containment atmosphere radioactivity monitoring channels inoperable (i.e., the required primary containment atmosphere monitoring system), grab samples of the primary containment atmosphere must be taken and analyzed to provide periodic LEAKAGE information. Provided a sample is obtained and analyzed once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, the plant may be operated for up to 30 days to allow restoration of at least one of the required monitors.

The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> interval provides periodic information that is adequate to detect LEAKAGE. The 30 day Completion Time for restoration recognizes that at least one other form of leakage detection is available.

C.1 and C.2 If any Required Action and associated Completion Time of Condition A or B cannot be met, or with all required monitors inoperable, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowed Completion Times are reasonable, based on operating experience, to perform the actions in an orderly manner and without challenging plant systems.

(continued)

Brunswick Unit 1 B 3.4.5-3 Revision No. 43 l

BSEP 05-0109 Enclosure 4 Unit 2 Technical Specification Bases Replacement Pages

Unit 2 - Bases Book 1 Replacement Pages

,,1 BASES TO THE FACILITY OPERATING LICENSE DPR-62 TECHNICAL SPECIFICATIONS FOR BRUNSWICK STEAM ELECTRIC PLANT UNIT 2 CAROLINA POWER & LIGHT COMPANY REVISION 41

LIST OF EFFECTIVE PAGES - BASES Page No. Revision No. Page No. Revision No.

Title Page 41 B 3.1.1-6 30 I B 3.1.2-1 30 List of Effective Pages - Book 1 B 3.1.2-2 30 B 3.1.2-3 30 LOEP-1 41 B 3.1.2-4 30 I LOEP-2 37 B 3.1.2-5 30 LOEP-3 39 B 3.1.3-1 30 LOEP-4 35 B 3.1.3-2 30 B 3.1.3-3 30 i 40 B 3.1.3-4 30 ii 30 B 3.1.3-5 30 B 3.1.3-6 30 B 2.1.1-1 30 B 3.1.3-7 30 B 2.1.1-2 30 B 3.1.3-8 30 B 2.1.1-3 30 B 3.1.3-9 30 B 2.1.1-4 30 B 3.1.4-1 30 B 2.1.1-5 30 B 3.1.4-2 30 B 2.1.2-1 30 B 3.1.4-3 30 B 2.1.2-2 30 B 3.1.4-4 30 B 2.1.2-3 30 B 3.1.4-5 40 B 3.1.4-6 30 B 3.0-1 30 B 3.1.4-7 30 B 3.0-2 30 B 3.1.5-1 30 B 3.0-3 30 B 3.1.5-2 30 B 3.0-4 30 B 3.1.5-3 30 B 3.0-5 39 B 3.1.5-4 30 B 3.0-6 39 B 3.1.5-5 30 B 3.0-7 39 B 3.1.6-1 30 B 3.0-8 39 B 3.1.6-2 30 B 3.0-9 39 B 3.1.6-3 30 B 3.0-10 39 B 3.1.6-4 30 B 3.0-11 39 B 3.1.6-5 30 B 3.0-12 39 B 3.1.7-1 30 B 3.0-13 39 B 3.1.7-2 30 B 3.0-14 39 B 3.1.7-3 30 B 3.0-15 39 B 3.1.7-4 30 B 3.0-16 39 B 3.1.7-5 30 B 3.0-17 39 B 3.1.7-6 30 B 3.1.8-1 30 B 3.1.1-1 30 B 3.1.8-2 34 B 3.1.1-2 30 B 3.1.8-3 34 B 3.1.1-3 30 B 3.1.8-4 30 B 3.1.1-4 30 B 3.1.8-5 30 B 3.1.1-5 30 (continued)

Brunswick Unit 2 LOEP-1 Revision 41 l

a.

TABLE OF CONTENTS B 2.0 SAFETY LIMITS (SLs) .................................................... B 2.1.1-1 B 2.1.1 Reactor Core SLs ...................................................... B 2.1.1-1 B 2.1.2 Reactor Coolant System (RCS) Pressure SL .......................................... B 2.1.2-1 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY ............B 3.0-1 B 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY ............................ B 3.0-11 B 3.1 REACTIVITY CONTROL SYSTEMS .................................................... B 3.1.1-1 B 3.1.1 SHUTDOWN MARGIN (SDM) .................................................... B 3.1.1-1 B 3.1.2 Reactivity Anomalies .................................................... B 3.1.2-1 B 3.1.3 Control Rod OPERABILITY .................................................... B 3.1.3-1 B 3.1.4 Control Rod Scram Times ...................................................... B 3.1.4-1 B 3.1.5 Control Rod Scram Accumulators ...................................................... B 3.1.5-1 B 3.1.6 Rod Pattern Control ......................................................B 3.1.6-1 B 3.1.7 Standby Liquid Control (SLC) System .................................................... B 3.1.7-1 B 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves ........................ B 3.1.8-1 B 3.2 POWER DISTRIBUTION LIMITS .................................................... B 3.2.1-1 B 3.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) ........................................... B 3.2.1-1 B 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR) ...................................... B 3.2.2-1 B 3.2.3 Fraction of Core Boiling Boundary (FCBB) ......................................... B 3.2.3-1 B 3.3 INSTRUMENTATION ........................................... B 3.3.1.1-1 B 3.3.1.1 Reactor Protection System (RPS) Instrumentation ................................. B 3.3.1.1-1 B 3.3.1.2 Source Range Monitor (SRM) Instrumentation ....................................... B 3.3.1.2-1 B 3.3.1.3 Period Based Detection System (PBDS) ......................................... B 3.3.1.3-1 B 3.3.2.1 Control Rod Block Instrumentation ......................................... B 3.3.2.1-1 B 3.3.2.2 Feedwater and Main Turbine High Water Level Trip Instrumentation ...................................... B 3.3.2.2-1 B 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation .................................... B 3.3.3.1-1 B 3.3.3.2 Remote Shutdown Monitoring Instrumentation ...................................... B 3.3.3.2-1 B 3.3.4.1 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation ................................................. B 3.3.4.1-1 B 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation ....................B 3.3.5.1-1 B 3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation ............B 3.3.5.2-1 B 3.3.6.1 Primary Containment Isolation Instrumentation ....................................... B 3.3.6.1-1 B 3.3.6.2 Secondary Containment Isolation Instrumentation .................................. B 3.3.6.2-1 B 3.3.7.1 Control Room Emergency Ventilation (CREV) System Instrumentation ........ B 3.3.7.1-1 (continued)

Brunswick Unit 2 Revision No. 40 l

a IV A#

Control Rod Scram Times B 3.1.4 BASES SURVEILLANCE SR 3.1.4.2 REQUIREMENTS (continued) Additional testing of a sample of control rods is required to verify the continued performance of the scram function during the cycle. A representative sample contains at least 10% of the control rods. The sample remains representative if no more than 7.5% of the control rods in the sample tested are determined to be "slow." With more than 7.5% of I the sample declared to be "slow" per the criteria in Table 3.1.4-1, additional control rods are tested until this 7.5% criterion (i.e., 7.5% of the I entire sample size) is satisfied, or until the total number of "slow" control rods (throughout the core, from all surveillances) exceeds the LCO limit.

For planned testing, the control rods selected for the sample should be different for each test. This test is performed for each control rod in the sample from its fully withdrawn position. Data from inadvertent scrams should be used whenever possible to avoid unnecessary testing at power, even if the control rods with data may have been previously tested in a sample. The 200 day Frequency is based on operating experience that I has shown control rod scram times do not significantly change over an operating cycle. This Frequency is also reasonable based on the additional Surveillances done on the CRDs at more frequent intervals in accordance with LCO 3.1.3 and LCO 3.1.5, "Control Rod Scram Accumulators."

SR 3.1.4.3 When work that could affect the scram insertion time is performed on a control rod or the CRD System, testing must be done to demonstrate that each affected control rod retains adequate scram performance over the range of applicable reactor pressures from zero to the maximum permissible pressure. The scram testing must be performed once before declaring the control rod OPERABLE. The required scram time testing must demonstrate the affected control rod is still within acceptable limits.

This test is performed for each affected control rod from its fully withdrawn position. In lieu of actually initiating a scram for each affected control rod, testing that adequately demonstrates the scram times are within acceptable limits is allowed to satisfy this SR. The test may include any series of sequential, overlapping, or total steps so the entire scram (continued)

Brunswick Unit 2 B 3.1.4-5 Revision No. 40 l

Iw' a Unit 2 - Bases Book 2 Replacement Pages

4 *VPt LIST OF EFFECTIVE PAGES - BASES Page No. Revision No. Paae No. Revision No.

Title Page N/A B 3.4.7-4 39 B 3.4.7-5 39 List of Effective Pages - Book 2 B 3.4.8-1 30 B 3.4.8-2 30 LOEP-1 41 B 3.4.8-3 30 LOEP-2 39 B 3.4.8-4 30 LOEP-3 39 B 3.4.8-5 30 LOEP-4 30 B 3.4.9-1 30 LOEP-5 30 B 3.4.9-2 35 B 3.4.9-3 35 30 B 3.4.9-4 30 ii 30 B 3.4.9-5 35 B 3.4.9-6 35 B 3.4.1-1 30 B 3.4.9-7 30 B 3.4.1 -2 30 B 3.4.9-8 30 B 3.4.1-3 30 B 3.4.9-9 35 B 3.4.1-4 30 B 3.4.10-1 30 B 3.4.1-5 30 B 3.4.10-2 30 B 3.4.1-6 30 B 3.4.2-1 30 B 3.5.1-1 30 B 3.4.2-2 30 B 3.5.1-2 30 B 3.4.2-3 30 B 3.5.1-3 30 B 3.4.2-4 30 B 3.5.1-4 33 B 3.4.3-1 30 B 3.5.1-5 33 B 3.4.3-2 30 B 3.5.1-6 39 B 3.4.3-3 30 B 3.5.1-7 30 B 3.4.3-4 30 B 3.5.1-8 30 B 3.4.4-1 30 B 3.5.1-9 30 B 3.4.4-2 30 B 3.5.1-10 30 B 3.4.4-3 30 B 3.5.1 -11 30 B 3.4.4-4 30 B 3.5.1-12 30 B 3.4.4-5 30 B 3.5.1-13 30 B 3.4.5-1 30 B 3.5.1-14 30 B 3.4.5-2 30 B 3.5.1-15 30 B 3.4.5-3 41 B 3.5.1-16 30 B 3.4.5-4 39 B 3.5.1-17 30 B 3.4.6-1 39 B 3.5.2-1 30 B 3.4.6-2 39 B 3.5.2-2 30 B 3.4.6-3 39 B 3.5.2-3 30 B 3.4.7-1 30 B 3.5.2-4 30 B 3.4.7-2 30 B 3.5.2-5 30 B 3.4.7-3 39 B 3.5.2-6 30 B 3.5.3-1 30 B 3.5.3-2 39 (continued)

Brunswick Unit 2 LOEP-1 Revision 41 l

4 A. 6 RCS Leakage Detection Instrumentation B 3.4.5 BASES (continued)

APPLICABILITY In MODES 1, 2, and 3, leakage detection systems are required to be OPERABLE to support LCO 3.4.4. This Applicability is consistent with that for LCO 3.4.4.

ACTIONS A.1 With the drywell floor drain sump flow monitoring system inoperable, no other required instrumentation can provide the equivalent information to quantify LEAKAGE. However, the primary containment atmosphere radioactivity monitor will provide indication of changes in LEAKAGE.

With the drywell floor drain sump flow monitoring system inoperable, but with RCS unidentified and total LEAKAGE being determined every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (SR 3.4.4.1), operation may continue for 30 days. The 30 day Completion Time of Required Action A.1 is acceptable, based on operating experience, considering the multiple forms of leakage detection that are still available.

B.1 and B.2 With both gaseous and particulate primary containment atmosphere radioactivity monitoring channels inoperable (i.e., the required primary containment atmosphere monitoring system), grab samples of the primary containment atmosphere must be taken and analyzed to provide periodic LEAKAGE information. Provided a sample is obtained and analyzed once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, the plant may be operated for up to 30 days to allow restoration of at least one of the required monitors.

The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> interval provides periodic information that is adequate to detect LEAKAGE. The 30 day Completion Time for restoration recognizes that at least one other form of leakage detection is available.

C.1 and C.2 If any Required Action and associated Completion Time of Condition A or B cannot be met, or with all required monitors inoperable, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowed Completion Times are reasonable, based on operating experience, to perform the actions in an orderly manner and without challenging plant systems.

(continued)

Brunswick Unit 2 B 3.4.5-3 Revision No. 41 l

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