ML20205K737

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Amends 227 & 230 to Licenses DPR-44 & DPR-56,respectively, Consisting of Changes to TS SRs Re Secondary Containment Doors in Response to 980204 Application,As Revised by
ML20205K737
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 04/07/1999
From: Clifford J
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20205K734 List:
References
NUDOCS 9904130362
Download: ML20205K737 (12)


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UNITED STATES ye j

j NUCLEAR REGULATORY COMMISSION

's WASHINGTON, D.C. 20555 0001

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l PECO ENERGY COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. ??7 License No. DPR-44 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by PECO Encrgy Company, et al. (the licensee) dated February 4,1998, as revised September 29,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I.

B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. DPR-44 is hereby amended to read as follows:

9904130362 990407 PDR ADOCK 05000277 P

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> (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.227, are hereby incorporated in the license. PECO Energy j

Company shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of issuance, to be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION sva/9 0 s)

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James W. Clifford, Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications i

Date of issuance: April 7,1999 4

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ATTACHMENTTO LICENSE AMENDMENT NO. zr/

FACILITY OPERATING LICENSE NO. DPR-44 DOCKET NO. 50-277 i

l-Replace the following pages of the Appendix A Technical Specifications with the enclosed l

pages. The revised areas are indicated by marginallines.

I Remove Insert 3.6-35 3.6-35 B 3.6-76 B 3.6-76 8 3.6-77 B 3.6-77

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Secondary Containment 3.6.4.1 ACTIONS CONDITION PEQUIRED ACTION COMPLETION TIME C.

(continued)

C.2 Suspend CORE Immediately ALTERATIONS.

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C.3 Initiate action to Immediately suspend OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1.1 Verify all secondary containment 31 days equipment hatches are closed and sealed.

SR 3.6.4.1.2 Verify one secor: s, cent;'ere ' e ?ss 31 days door in each eces:s r>en\\nq in e*

SR 3.. 4.1.3 Verify each staadby ga treatment (SGT) 24 months on a subsystem will draw down tha secondary STAGGERED TEST containment to 2 0.25 inch of vacuum BASIS water gauge in s 120 seconds.

SR 3.6.4.1.4 Verify each SGT subsystem can maintain 24 months on a 2 0.25 inch of vacuum water gauge in the STAGGERED TEST secondary containment for I hour at a BASIS flow rate s 10,500 cfm.

PBAPS UNIT 2 3.6-35 Amendment No.,,77 i

Secondary Containment B 3.6.4.1 l

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. BASES (continued)

SURVEILLANCE SC 3.6 4.1.1 and SR 3.6.4.1.2 l

REQUIREMENTS Verifying that secondary containment equipment hatches and

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one access door in each access opening are closed ensures that the infiltration of outside air of such a magnitude as i

to prevent maintaining the desired negative pressure does not occur. Verifying that all such openings are closed provides adequate assurance that exfiltration from the secondary cor.?ainment will not occur.

In this application, the term " sealed" has no connotation of leak tightness.

Maintaining secondary containsnent OPERABILITY requires l

verifying one door in the access opening is closed. An access opening contains one inner and one outer door.

In some cases, secondary containment access openings are shared such that a secondary containment barrier may have multiple inner or multiple outer doors. The intent is to not breach secondary containment at any time when secondary containment is required. This is achieved by maintaining the inner or outer portion of the barrier closed at all times. However, all secondary containment access doors are normally kept l

closed, except when the access opening is being used for entry and exit or when maintenance is being performed on an access opening. The 31 day Frequency for these SRs has been shown to be adequate, based on operating experience, and is considered adequate in view of the other indications of door and hatch status that are available to the operator.

I SR 3.6.4.1.3 and SR 3.6.4.1.4 The SGT System exhausts the secondary containment atmosphere to the environment through appropriate treatment equipment.

j To ensure that fission products are treated, SR 3.6.4.1.3 verifies that the SGT System will rapidly establish and maintain a pressure in the secondary containment that is less than the pressure external to the secondary containmei.i.

boundary. This is confirmed by demonstrating that one SGT subsystem will draw down the secondary containment to i

a 0.25 inches of vacuum water gauge in s 120 seconds. This cannot be accomplished if the secondary containment boundary is not intact.

SR 3.6.4.1.4 demonstrates that one SGT subsystem can l

l maintain 2 0.25 inches of vacuum water gauge for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at a flow rate s 10,500 cfm. The I hour test period allows secondary containment to be in thermal equilibrium at steady (continued)

PBAPS UNIT 2 B 3.6-76 Revision No.

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Secondary Containment B 3.6.4.1 I

. BASES SURVEILLANCE SR 3.6.4.1.3 and SR 3.6.4.1.4 (continued)

REQUIREMENTS state conditions. Therefore, these two tests are used to ensure secondary containment boundary integrity.

Since these SRs are secondary containment tests, they need not be performed with each SGT subsystem. The SGT. subsystems are i

l tested on a STAGGERED TEST BASIS, however, to ensure that in addition to the requirements of LCO 3.6.4.3, either SGT subsystem will perform this test. Operating experience has shown these components will usually pass the Surveillance when performed at the 24 month Frequency. Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.

REFERENCES 1.

UFSAR, Se. tion 14.6.3.

2.

UFSAR, Section 14.6.4.

l PBAPS UNIT 2 B 3.6-77 Revision No.

kenrhent No. ??7

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4 UNITED STATES 2.L 8

NUCLEAR REGULATORY CCMMISSION f

WASHINGTON, D.C. 2055fHX)01

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PECO ENERGY COMPAN't PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND llGHT COMPANY ATLANTIC CITY ELF.CTRIC COMPANY DOCh6T NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 230 License No. DPR-56 i

1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by PECO Energy Company, et al. (the licensee) dated February 4,1998, as revised September 29,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), end the Commission's rules and regulations set forth in 10 CFR Chapter 1.

B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment l

can be conducted without endangering the health and safety of the public, and (ii)

I that such activities will be conducted in compliance with the Commission's l

regulations; D.

The issuance of this amendment will not be inimical to the common defense and i

security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility l

Operating License No. DPR-56 is hereby amended to read as follows.

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(2) Technical Specifications-I-

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The Technical Specifications contained in Appendices A and B, as revised through I

Amendment No. 230, are hereby incorporated in the license. PECO shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of issuance, to be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION uVclh.

id Jan)es W. Clifford, Chief, Section 2 Project Directorate i Division of Licensing Project Management l

Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications l

Date of issuance: April 7,1999 l

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ATTACHMENT TO LICENSE AV.CNDMENT NO. E i

FACILITY OPERATING LICENSE NO. DPR-56 DOCKET NO. 50-278 1

l Replace the following par. '

'the Appendix A Technical Specifications with the enclosed l

pages. The revised ar-indicated by marginallines.

Remove Insert i

j 3.6-35 3.S-35 B 3,6-76 B 3.6-76 B 3.6-77 B 3.6-77

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Secondary Containment i

3.6.4.1 ACTIONS l

CONDITION REQUIRED ACTION COMPLETION TIME C.

(continued)

C.2 Suspend CORE Immediately ALTERATIONS.

AND C.3 Initiate action to Immediately suspend OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1.1 Verify all secondary containment 31 days equipment hatches are closed and sealed.

SR 3.6.4.1.2 Verify one secondary containment access 31 days door in each access opening is closed.

SR 3.6.4.1.3 Verify each standby gas treatment (SGT) 24 months on a subsystem will draw down the secondary STAGGERED TEST containment to a 0.25 inch of vacuum BASIS water gauge in s 120 seconds.

SR 3.6.4.1.4 Verify each SGT subsystem can maintain 24 months on a 2 0.25 inch of vacuum water gauge in the STAGGERED TEST secondary containment for I hour at a BASIS flow rate s 10,500 cfm.

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l PBAPS UNIT 3 3.6-35 Amendment No 733

Secondary Containment j*

B 3.6.4.1

. BASES (continued)

SURVEILLANCE SR 3.6.4.1.1 and SR 3.6.4.1.2 REQUIREMENTS Verifying that secondary containment equipment hatches and l

one access door in each access opening are closed ensures that the infiltration of outside air of such a magnitude as to prevent maintaining the desired negative pressure does not occur. Verifying that all such openings are closed provides adequate assurance that exfiltration from the

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j secondary containment will not occur.

In this application, 1

the tern " sealed" has no connotation of leak tightness.

Maintaining secondary containment OPERABILITY requires verifying one door in the access opening is closed. An access opening contains one inner and one out6r door.

In 3

some cases, secondary containment access openings are shared such that a secondary containment barrier may have multiple inner or multiple outer doors. The intent is to not breach secondary containment at any time when secondary containment is required. This is achieved by maintaining the inner or outer portion of the barrier closed at all times. However, all secondary containment access doors are normally kept closed, except when the access opening is being used for entry and exit or when maintenance is being performed on an access opening. The 31 day Frequency for these SRs has been shown to be adequate, based on operating experience, and is censidered adequate in view of the other indications of door and hatch status that are available to the operator.

SR 3.6.4.1.3 and SR 3.6.4.1.4 The SGT System exhausts the secondary containment atmosphere to the environment through appropriate treatment equipment.

To ensure that fission products are treated, SR 3.6.4.1.3 verifies that the SGT System will rapidly establish and maintain a pressure in the secondary containment that is less than the pressure external to the secondary containment boundary.

This is confirmed by demonstrating that one SGT subsystem will draw down the secondary containment to 2 0.25 inches of v3cuum water gauge in s 1-20 seconds. This cannot be accomplished if the secondary containment boundary is not intact.

SR 3.6.4.1.4 demonstrates that one SGT subsystem can maintain 2 0.25 inches of vacuum water gauge for I hour at a flow rate s 10,500 cfm. The I hour test period allows secondary containment to be in thermal equilibrium at steady (continued)

PBAPS UNIT 3 B 3.6-76 Revision No.

trmtmt % W

Secondary Containment B 3.6.4.1 r

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. BASES SURVEILLANCE SR 3.6,4.1.3 and SR 3.6,4.1.4 (continued)

REQUIREMENTS state conditions.

Therefore, these two tests are used to

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ensure secondary containment boundary integrity.

Since-these SRs are secondary containment tests, they need not be performed with each SGT subsystem. The SGT subsystems are tested on a STAGGERED TEST BASIS, however, to ensure that in addition to the requirements of LCO 3.6.4.3, either SGT subsystem will perform this test. Operating experience has shown these components will usually pass the Surveillance when performed at the 24 month Frequency.

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

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1 REFERENCES 1.

UFSAR, Section 14.6.3.

2.

UFSAR, Section 14.6.4.

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i PBAPS UNIT 3 8 3.6-77 Revision No.

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