Text

Submittal of Technical Specification Bases Changes for Revision 20
	ML020650248
Person / Time
Site:	Brunswick
Issue date:	02/20/2002
From:	Beller L; Carolina Power & Light Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	BSEP 02-0047
	Download: ML020650248 (23)
	v • d • e

K CP&L A Progress Energy Company FEB 2 0 2002 SERIAL: BSEP 02-0047 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324/LICENSE NOS. DPR-71 AND DPR-62 SUBMITTAL OF TECHNICAL SPECIFICATION BASES CHANGES FOR REVISION 20 Ladies and Gentlemen:

In accordance with Technical Specification (TS) 5.5.10.d for the Brunswick Steam Electric Plant (BSEP), Unit Nos. 1 and 2, Carolina Power & Light (CP&L) Company is submitting Revision 20 to the BSEP Unit 1 and Unit 2 TS Bases. Enclosure 1 provides a description of the revision, the date of implementation, and the BSEP units affected. Instructions for replacing the pages contained in the TS Bases books are provided in Enclosure 2. provides replacement TS Bases pages for both BSEP units.

Please refer any questions regarding this submittal to Mr. Steven F. Tabor, Supervisor Licensing/Regulatory Programs, at (910) 457-2178.

Sincerely, Leonard R. Beller Manager - Regulatory Affairs Brunswick Steam Electric Plant KMN/kmn

Enclosures:

1. Summary of Revision to Technical Specification Bases

2. Technical Specification Bases Pages Replacement Instructions

3. Replacement Bases Pages - Units 1 and 2 Brunswick Nuclear Plant P.O. Box 10429 (Do Southport, NC 28461

Document Control Desk BSEP 02-0047 / Page 2 cc (with enclosures):

U. S. Nuclear Regulatory Commission, Region II ATTN: Mr. Luis A. Reyes, Regional Administrator Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-8931 U. S. Nuclear Regulatory Commission ATTN: Mr. Theodore A. Easlick, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission (Electronic Copy Only)

ATTN: Mr. Allen G. Hansen (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 27626-05 10 Mr. Mel Fry Director - Division of Radiation Protection North Carolina Department of Environment and Natural Resources 3825 Barrett Drive Raleigh, NC 27609-7221

BSEP 02-0047 Page 1 of 1 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324/LICENSE NOS. DPR-71 AND DPR-62 SUBMITTAL OF TECHNICAL SPECIFICATION BASES CHANGES FOR REVISION 20 Summary of Revision to Technical Specification Bases Summnary of Revision to Technical Specification Bases Revision Affected Units Date Implemented Title/Description 20 1 and 2 January 30, 2002

Title:

Control Room Emergency Ventilation System

==

Description:==

This Bases revision changed the number of control room supply fans required to maintain pressure positive from two to one.

BSEP 02-0047 Page 1 of 1 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324/LICENSE NOS. DPR-71 AND DPR-62 SUBMITTAL OF TECHNICAL SPECIFICATION BASES CHANGES FOR REVISION 20 Technical Specification Bases Pages Replacement Instructions Unit I Remove Bases Book 1 Title Page, Revision 19 Title Page, Revision 20 LOEP-1, Revision 19 LOEP-1, Revision 20 Bases Book 2 LOEP-1, Revision 19 LOEP-3, Revision 20 LOEP-3, Revision 18 LOEP-3, Revision 20 B 3.7-21, Revision 9 B 3.7-21, Revision 20 B 3.7-23, Revision 9 B 3.7-23, Revision 20 B 3.7-27, Revision 11 B 3.7-27, Revision 20 Bases Book 1:

Title Page, Revision 19 Title Page, Revision 20 LOEP-1, Revision 19 LOEP-1, Revision 20 Bases Book 2 LOEP-3, Revision 19 LOEP-3, Revision 20 LOEP-3, Revision 18 LOEP-3, Revision 20 B 3.7-21, Revision 10 B 3.7-21, Revision 20 B 3.7-23, Revision 10 B 3.7-23, Revision 20 B 3.7-27, Revision 11 B 3.7-27, Revision 20

ENCLOSURE 3 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324/LICENSE NOS. DPR-71 AND DPR-62 SUBMITTAL OF TECHNICAL SPECIFICATION BASES CHANGES FOR REVISION 20 Relacement Bases Panes - Units I and 2

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 20

LIST OF EFFECTIVE Page No.

Revision No.

Title Page 20 List of Effective Pages - Book I LOEP-1 LOEP-2 LOEP-3 LOEP-4 i ii 2.0-1 2.0-2 2.0-3 2.0-4 2.0-5 2.0-6 2.0-7 2.0-8 3.0-1 3.0-2 3.0-3 3.0-4 3.0-5 3.0-6 3.0-7 3.0-8 3.0-9 3.0-10 3.0-11 3.0-12 3.0-13 3.0-14 3.0-15 3.1-1 3.1-2 3.1-3 3.1-4 3.1-5 3.1-6 20 3

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Revision 20 1 LOEP-3

CREV System B 3.7.3 B 3.7 PLANT SYSTEMS B 3.7.3 Control Room Emergency Ventilation (CREV)

System BASES BACKGROUND The CREV System provides a radiologically controlled environment from which the unit can be safely operated following a Design Basis Accident (DBA).

The safety related function of CREV System is the radiation protection portion of the radiation/smoke protection mode and includes two redundant high efficiency air filtration subsystems for emergency treatment of recirculated air or outside supply air.

Each subsystem consists of a high efficiency particulate air (HEPA) filter, an activated charcoal adsorber bank, an emergency recirculation fan, and the associated ductwork and dampers.

HEPA filters remove particulate matter, which may be radioactive.

The charcoal adsorber banks provide a holdup period for gaseous iodine, allowing time for decay.

One control room supply fan provides the required flow to maintain the pressure of the control room positive with respect to the outside atmosphere.

The CREV System is a standby system that is common to both Unit 1 and Unit 2, parts of which also operate during normal unit operations to maintain the control room environment.

The two CREV subsystems must be OPERABLE if conditions requiring CREV System OPERABILITY exist in either Unit I or Unit 2.

Upon receipt of the initiation signal(s)

(indicative of conditions that could result in radiation exposure to control room personnel), the CREV System automatically switches to the radiation/smoke protection mode of operation to prevent infiltration of contaminated air into the control room.

A system of dampers isolates the control room, and a part of the recirculated air is routed through either of the two filter subsystems.

Outside air is taken in at the normal ventilation intake and is mixed with the recirculated air before being passed through one of the CREV subsystems for removal of airborne radioactive particles.

(continued)

Brunswick Unit 1 Revision No.

20 B 3.7-21

CREV System B 3.7.3 BASES LCO (continued)

c.

Ductwork, valves, and dampers are OPERABLE, and air circulation can be maintained.

Also, two control room supply fans must be OPERABLE to ensure positive pressure can be maintained in the control room with respect to the outside atmosphere and to meet single failure criteria.

In addition, the control room boundary must be maintained, including the integrity of the walls, floors, ceilings, ductwork, and access doors, such that SR 3.7.3.3 can be met.

However, it is acceptable for access doors to be opened for normal control room entry and exit and not consider it to be a failure to meet the LCO.

APPLICABILITY In MODES 1, 2, and 3, the CREV System must be OPERABLE to control operator exposure during and following a DBA, since the DBA could lead to a fission product release.

In MODES 4 and 5, the probability and consequences of a DBA are reduced because of the pressure and temperature limitations in these MODES.

Therefore, maintaining the CREV System OPERABLE is not required in MODE 4 or 5, except for the following situations under which significant radioactive releases can be postulated:

a.

During movement of irradiated fuel assemblies in the secondary containment;

b.

During CORE ALTERATIONS; and

c.

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

ACTIONS A.I With one CREV subsystem inoperable, the inoperable CREV subsystem must be restored to OPERABLE status within 7 days.

With the unit in this condition, the remaining OPERABLE CREV subsystem is adequate to perform control room radiation protection.

However, the overall reliability is reduced because a single failure in the OPERABLE subsystem could result in reduced CREV System capability.

The 7 day (continued)

Revision No.

20 1 I

B 3.7-23 Brunswick Unit 1

CREV System B 3.7.3 BAS ES SURVEILLANCE REQUIREMENTS SR 3.7.3.3 (continued)

CREV System is designed to maintain this positive pressure at a flow rate of < 2200 cfm to the control room in the radiation/smoke protection mode.

To adequately demonstrate the capability of a CREV subsystem to maintain positive pressure, no more than one control room supply fan may be in operation during performance of this test.

The Frequency of 18 months on a STAGGERED TEST BASIS is based on the low probability of significant degradation of the control room boundary occurring between surveillances.

SR 3.7.3.4 This SR verifies that on an actual or simulated initiation signal, each CREV subsystem starts and operates.

This SR includes ensuring outside air flow is diverted to the HEPA filter and charcoal adsorber bank of each CREV subsystem.

The LOGIC SYSTEM FUNCTIONAL TEST in LCO 3.3.7.1 overlaps this SR to provide complete testing of the safety function.

Operating experience has demonstrated that the components will usually pass the SR when performed at the 24 month Frequency.

Therefore, the Frequency was found to be acceptable from a reliability standpoint.

REFERENCES

1.

UFSAR, Section 6.4.

2.

UFSAR, Section 9.4.

3.

UFSAR, Section 15.6.4.5.5.

4.

10 CFR 50.36(c)(2)(ii).

5.

ESR 99-00055, SBGT and CBEAF Technical Specification Surveillance Flow Measurement.

Revision No.

20 1 Brunswick Unit 1 B 3.7-27

Unit 2 Bases Book 1 Replacement Pages

BASES TO THE FACILITY OPERATING LICENSE DPR-62 TECHNICAL SPECIFICATIONS FOR BRUNSWICK STEAM ELECTRIC PLANT UNIT 2 CAROLINA POWER & LIGHT COMPANY REVISION 20

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