ML20205T236

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Application for Amends to Licenses DPR-62 & DPR-71, Clarifying Svc Water Pump Operability Requirements to Better Reflect Plant Design & Provide Operational Flexibility.Fee Paid
ML20205T236
Person / Time
Site: Brunswick  
Issue date: 11/03/1988
From: Mcduffie M
CAROLINA POWER & LIGHT CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20205T239 List:
References
NLS-88-118, NUDOCS 8811140180
Download: ML20205T236 (9)


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  • e carenne power a uent company 1

P. O. Bos 1551 e Heleegn, N. o. 27002 NOV 3 ja M. A. McDUFFIE sen.or vice Preo+ dent fJucleet Generation SERIAL: NLS-88-il8 10CFR50.90 85TSB09 United States Nuclear Regulatory Commission

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ATTENTION: Document Control Desk Washington, DC 20535 BRUNSWICV. STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS, 50-325 & 50-324/LICEN3E NOS. DPR-71 & DPR-62 REQUEST FOR LICENSE AMENDMENT SERVICE WATER SYSTEM Gentlemen:

In accordance with the Code of Federal Regulations, Title 10, Parts 50.90 and 2.101, Carolina Power & Light Company (CP&L) hereby requests a revision to the Technical Specifications (TS) for the Brunswick Steam Electric Plant (BSEP), Units 1 and 2. The proposed change clarifies service water pump operability requirements to better reflect plant design and to provide greater operational flexibility. The TS Bases is also revised to reflect the proposed change.

I Enclosure i provides a detailed description of the proposed changes and the basis for the l

changes.

j details the basis for the Company's determination that the proposed changes do not involve a significant hazards consideration.

I provides instructions for incorporation of the proposed changes into the Technical Specifications for each unit.

i provides a summary of the proposed Technical Specification changes for each unit on a page by page basis.

Enck. ure 5 provides the proposed Technical Specification pages for Unit 1.

! provides the proposed Technical Specification pages for Unit 2.

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. NLS-38-ll3 / Page 2 In accordance with the requirements of 10CFR170.12, a check for $150 is alto enclosed.

Please refer any questions regarding this sobrnittal to Mr. Stephen D. Floyd at (919) 836-6901.

Yours very truly,

) $ l'I & f M. A. McDuf fie MAM/AWS/che (5471 AWS)

Enclosures:

1.

Basis for Change Request 2.

10CFR50.92 Evaluation 3.

Instructions for Incorporation 4.

Summary List of Revisions 5.

Technical Specification Pages - Unit i 6.

Technical Specification Pages - Unit 2 cc Mr. Dayne H. Brev n Mr. M. L. Ernst Mr. W. H. Rutand Mr. B. C. Buckley M. A. McDuf fie, having been first duly swo:n, did depose and say that the information contained herein is true and correct to the best of his information, knowledge and belief s and the sources of his information are of ficers employees, contractors, and agents of Carolina Power & Light Company.

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s, ENCLOSURE 1 BRUNSWICK STEAM ELECTRIC PLANT, UNITS l AND 2 NRC DOCKETS 50-325 & $0-324 OPERATING LICENSES DPR-71 & DPR-62 REQUEST FOR LICENSE AMENDMENT SERVICE WATER SYSTEM BASIS FOR CHANGE REQUEST Proposed Change i Presently TS Section 3.7.;.2 requires that at least three service water putops be operable to supply the service water system nuclear header. The proposed change revises this section to require that at least four service water pumps be operable while in OPERATIONAL CONDITIONS 1,2, and 3 to supply the service water system nuclear header while allowing credit to be taken for the system cross-connects between the two Brunswick units. Because of the credit taken for the unit cross-connect, the specificafion has been divided into two separate sections. The first section addresses service water system operability requirements with one or both of the Brunswick units operational. The secono'section addresses service water system operability requirements with both Brunswick units shutdown. The latter continues to require only three service water pun ps to be operable.

Proposed Change 2 The proposed change revises TS Bases Section 3/4.7.1 to reflect the basis for service water pump operability requirements described in proposed change 1.

Basis The service water system provides water for lubrication cooling and cooling of selected equipment in the turbine building, reactor building, diesel generator building, chlorination system, circulating water system, and screen wash system. The service v:ater system is subdivided into two major headers which are normally operated independently the nuclear header supplies service water to the nuclear or vital equipment in the reactor building and diesel generator building, and the conventional header normally supplies service water to conventional equipment in the turbine building and other areas. Two nuclear service water pumps (one operating, one standby) supply the nuclear header and three conventional service water pumps (two operating, one standbv) supply the conventional header for each unit. Cross-connect valves allow the conventtoi.al pumps to supply the nuclear header as conditions dictate. The two types of pumps are identical except that the nuclear service water pumps start automatically during a design basis accident (DBA)(loss-of-coolant accident, LOC A, coincident with a loss of of f-site power, LOOP) while the conventional service water pumps must be started manually under these conditions. The diesel generators, which are the only common load between the two Brunswick units, can receive cooling water from the nuclear header of either unit.

Either of the conventional or nuclear headers, or a combination of the two, can provide water to other loads including the Residual Heat Removal System (RiiR) room coolers, the RfiR pump seal heat exchangers, the core spray (CS) pump room coolers, and the RilR service water cooling system. The service water system can also be cross-connected to the RilR System during emergencies to provide core flooding capabilities, i

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a, Presently, the Technical Specifications (TS) Section 3.7.1.2, require each unit to have three service water pumps operable to supply the service water nuclear header. The proposed change does not alter the total number of operable service water pumps on site. The change does, however, clarify the number and type of service water pumps necessary to supply the service water system nuclear header. This allows greater operational flexibility and more closely reflects the actual plant design.

The proposed revision requires two operable nuclear service water pumps powered from different divisions. This specification may be satisfied by either aligning one pump from each unit or aligning two pumps from a single unit. Requirements for power supplies from different divisions assure that separation criteria are met, in addition to the two nuclear service water pumps, each individual unit must have two of its service water pumps (conventional or nuclear) operable, each powered from a different division.

United Engineers and Constructors, Inc. (UE&C) analysis indicates that during the initial rtage of a DBA (0-10 minutes), only service water cooling to the diesel generators is required. Plant design allows either unit's service water system to supply diesel generator cooling water; therefore, any combination of two nuclear service water pumps is acceptable, provided they are powered from dif ferent divisions. Analysis has shown t

that one pump can supply all four diesel generators; however, two pumps are required OPERABLE to meet the single failure criteria.

In the post accident stage (greater tt an 10 minutes), additional loads also require cooling water. These loads include RHR and CS pump room coolers, RHR service water heat i

exchangers, and RHR pump seals. UE&C evaluations indicate that the RHR pump seals, as well as the equipment in rooms serviced by the RHR and CS room coolers remain within the manufacturers temperature limits for the first ten minutes of a DBA. To meet the additional loads during the post-accident stage, a service water pump on the af fected unit (in addition to the pump supplying the diesels) must be placed in service, in i

order to assure single failure and separation criteria are met, the proposed TS change requires two operable service water pumps powered from dif ferent divisions.

With both units in OPERATIONAL CONDITIONS 4 nr 5, Technical Specifications (Section 3.8.2.2) require that one 4l60 volt emergev.y bus be OPERABLE per unit. The electrical power distribution system is such that with only one OPERABLE bus per unit, only one service water pump would be available to supply the service water system nuclear header (in addition to the two nuclear service water pumps per site supplying the diesel generators). Therefore, the requirement to have only one service water pump per unit while in OPERATIONAL CONDITIONS 4 or 3 is established. The ACTION requirements for the loss of the only required pump are established at 7 days. Tnis is consistent with the Appendix R criteria for a unit in OPERATIONAL CONDITIONS 4 or 5 l

i in that only one service water pump per unit must be isolated from fire hazard to insure l

operability.

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ENCLOSURE 2 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKETS 50-325 & 50-324 OPERATING LICENSES DPR-71 & DPR-62 REQUEST FOR LICENSE AMENDMENT SERVICE WATER SYSTEM 10CFR 50.92 EVALUATION The Commission has provided standards in 10CFR50.92(c) for determining whether a significant hazards consideration exists. A proposed amendment to an operating license for facility involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would nots (1) involve a significant increase in the probability or consequences of an accident previously evaluated. (2) create the l

possibility of a new or dif ferent kind of accident from any accident previously evaluated, or (3) involve a significant reduction in a margin of safety. Carolina Power &

Light Company has reviewed this proposed license amendment request and determined that its adoption would not involve a significant hazards consideration. The bases for this determination are as follows:

t Proposed Change I The proposed change revises the service water system operability requirements specified in TS Section 3.7.1.2. The proposed change divides the current specifications into two separate sections. The first section (3.7.l.2.1) addresses service water system operability requirements with one or both of the Brunswick units operational (four operable service water pumps required). The second section (3.7.1.2.2) addresses service l

water system operability requirements with both Brunswick units shutdown (three l

operable service water pump required).

Basis i

The changt does not involve a significant hazards consideration for the following reasons:

l 1.

There are no physical modifications of plant equipment or changes to setpoints as a rasult of this proposed change. The change merely allows the use of the t

present plant design and capabilities to ensure that an adequate supply of water is available for coohng of the diesel generators and other vital i

equipment. The proposed change requires an additional service water pump to be operable during OPER ATIONAL CONDITIONS t,2, and 3 while allowing the use of the cross-connect betw ten the Brunswick units. This additional pump I

will ensure the availability of service water for diesel generator omling during the initial 10 minute period of a design basis accident. This along with the requirement that the pumps be powered from dif ferent divisions assures that L

both single failure and separation criteria are met. Operability of the.ervice t

water system does not affect the probability of an accident since its primary function is to aid in limiting the coasequences once the accident has initiated. Since the system's availability is not af fected by the proposed change, the consequences will likewise be unaflected. Based on this reason;ng, CP&L has determined that the proposed amendn.ent does not involve a significant increase in the probability or consequences of an accident previously evaluated.

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The service water system is designed to provide lubrication and cooling of equipment during normal operations and under accident conditions. The system can also be cross-connected to the RHR system during emergencies to provide core flooding capabilities. The service water system aids in mitigation of an accident, but does not act as an initiator of an accident sequence. The proposed change does not af fect the ability of the service water system to perform its intended function. The proposed change does not involve i

modification of the service water system or changes to the system setpoints.

The system will continue to be available to provide an adequate supply of cooling water for both normal operations and during emergencies. Therefore.

the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.

L 3.

The proposed change clarifles service water pump operability requirements to l

better reflect plant design and to provide greater operational flexibility.

l There will be no physical alteration of the service water system tss a result of i

this change. The proposed change will provide the same level of assurance of service water system availability for both normal operations and accident l

conditions. Therefore, the proposed change does not involve a significant reduction in the margin of safety.

Proposed Change 2 The proposed change revises TS Bases Section 3/4.7.1 to reflect the basis for service water pump operability requirements described in proposed change 1.

I Basis A 10CFR30.92 significant hazards evaluation is not provided for this change since the Bases are only summary statements in support of the Technical Specifications, and are not considered part of the actual Technical Specifications consistent with the provisions i

of 10CFR30.36.

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ENCLOSURE 3 q

BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 t

1 NRC DOCKETS30-325 & 30-324 OPERATING LICENSES DPR-71 & DPR-62 REQUEST FOR LICEN.,E AMENDMENT l

SERVICE WATER SYSTEM r

INSTRUCTIONS FOR INCORPORATION The proposed changes to the Technical Specifications (Appendix A to Operating Licenses DPR-71 and DPR-62) would be incorporated as follows:

L UNIT 1 f

Remove Page Insert Page f

Vil VII XII Xil 3/47-2 3/47-2 i

3/4 7-2a 3/4 7-2a i

3/4 7-2b 3/4 7-2c r

B3/4 7-1 B3/4 7-1 l

B3/4 7-2 B3/4 7-2 i

B3/4 7-3 B3/4 7-3 i

I B3/4 7-4 B3/4 7-4 B3/4 7-5 B3/47-5

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B3/4 7 2 B3/4 7-2 I

B3/4 7-3 B3/4 7-3 B3/4 7-4 B3/4 7-4 i

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ENCLOSURE 4 k

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BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKETS 50-325 & 50-324 OPERATING LICENSES DPR-71 & DPR-62 REQUEST FO( LICENSE AMENDMENT SERVICE WATER SYSTEM l

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SUMMARY

LIST OF REVISIONS UNIT l Pages Description of Changes l

VII Revises the page number reference for f

the service water system due to the shif t in text 4

XII Revises the Bases section page reference for Plant Systems due to the

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d shif t in text t

3/47-2 Replaces service water system LCO c

3.7.1.2 with a new section 3.7.1.2.1 for

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operation of one or both units l

3/4 7-2a Replaces service water system LCO t

d 3.7.1.2 with a new section 3.7.1.2.1 for i

operation of one or both units i

I 3/4 7-2b Replaces service water system LCO 3.7.1.2 with a new section 3.7.1.2.2 for i

both units in a shutdown condition t

l 3/4 7-2c Replaces service water system LCO 3.7.1.2 with a new section 3.7.1.2.2 for i

both units in a shutdown condition f

B3/4 7-1 Revises Bases Section B3/4.7.1 to i

j reflect the proposed char.ge

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l B3/4 7-2 through Reformats the Bases Sections contained j

B3/4 7-5 on these pages to accommodate j

additional text l

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UNIT 2 i

Pages Description of Changes VII Revises the page number reference for the service water system due to the shif t in text i

XII Revises the Bases section page reference for Plant Systems due to the r

shif t in text l

3/47-2 Replaces service water system LCO 3.7.1.2 with a new section 3.7.1.2.1 for I

cperation of one or both units i

3/4 7-2a Replaces service water system LCO 3.7.l.2 with a new section 3.7.1.2.1 for operation of one or both units 3/4 7-2b Replaces service water system LCO 3.7.1.2 with a new section 3.7.1.2.2 for both units in a shutdown condition 3/4 7-2c Replaces service water system LCO 3.7.1.2 with a new section 3.7.1.2.2 for both units in a shutdown condition B3/47-1 Revises Bases Section B3/4.7.1 to a

reflect the proposed change l

B3'4 7-2 through Reformats the Bases Sections contained B'J/4 7-5 on these pages to accommodate t

additional text l

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