ML20154J022
| ML20154J022 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 10/01/1998 |
| From: | Capra R NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20154J026 | List: |
| References | |
| NUDOCS 9810150148 | |
| Download: ML20154J022 (10) | |
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UNITED STATES s
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 3000H001 L
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4 PHILADELPHIA ELECTRIC COMPANY DOCKET No. 50 352 LIMERICK GENERATING STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.130 l
License No. NPF-39
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1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company (the licensee) dated March 24,1997, as supplemented September 4,1998, 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, j
i 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 sati-sfied.
9810150148 981001 E
PDR ADOCK 05000352 P
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UNITED STATES p
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p NUCLEAR REGULATORY COMMISSION l
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WAsHINGTOJ, D.C. 30006 4001
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October 1, 1998 Mr. Garrett D. Edwards l
Director-Uconsing, MC 62A-1 l
PECO Energy Company Nuclear Group Headquarters Correspondence Control Desk P.O. Box No.195 l
Wayne, PA 19087-0195
SUBJECT:
UMERICK GENERATING STATION, UNITS 1 AND 2 (TAC NOS. M98421 and M98422)
Dear Mr. Edwards:
The Commission has issued the enclosed Amendraent No.130 to Facility Operating Ucense No.
NPF-39 and Amendment No. 91 to Facility Operating Ucense No. NPF-85 for the Umerick Generating Station, Units 1 and 2. These amendments consist of changes to the Technical Specifications (TSs) in response to your application dated March 24,1997, as supplemented September 4,1998.
These amendments approve the deletion of the Drywell and Suppression Chamber Purge System operational time limit, removal of a footnote regarding 1-inch and 2-inch valves, and the addition of a surveillance requirement ensuring the purge system large supply and exhaust valves are closed as required.
A copy of our safety evaluation is also enclosed. Notice of issuance will be included in the Commission's biweekly Federal Renister notice.
This concludes our effort on this issue and we are, therefore, closing out TAC Nos. M98421 and
. M98422.
Sincerely,
%d 0
Bartholomew C. Buckley, Senior Project Manager Project D! rectorate 1-2 Division of Reactor Projects - t/il Office of Nuclear Reactor R3gulation Docket Nos. 50 352/353
Enclosures:
- 1. Amendment No130to Ucense No. NPF-39 l
- 2. Amendment No.91to l
Ucense No. NPF-85
' 3. Safety Evaluation
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2-2.
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 Ucense No. NPF-39 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.130. are hereby incorporated into this license. Philadelphia Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
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3.
This license amendment is effective as of its date of issuance, and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Tal.1a,C w Robert A. Capra, Director Project Directorate 1-2 Division of Reactor Projects - t/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: (htober 1,1998 l
l 1
ATTACHMENT TO LICENSE AMENDMENT NO.i tn FACILITY OPERATING LICENSE NO. NPF-39 DOCKET NO. 50-352 Replace the following peges of the Appendix A Techn! cal Specifications with the attached pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the l
area of change.
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Remove 10and W4 611 W4 611 BW462 B W 4 6-2
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3 CONTAINMENT SYSTEMS DRYWELL AND SUPPRESSION CHAMBER PURGE SYSTEM LIMITING CONDITION FOR OPERATION
.3.6.1.8 The drywell and suppression chamber purge system may be in operation with the supply and exhaust isolation. valves in one supply line and one exhaust line open for inerting, deinerting, pressure control, ALARA or air quality considerations for personnel entry, or Surveillances that require the valves to be open.
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APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION:
a.
With a' drywell and/or suppression chamber purge supply and/or exhaust isolation valve open, except as permitted above, close'the valve (s)
. within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE RE0VIREMENTS I
4.6.1.8 At'least once per 31 days, verify each primary containment purge valve [18" or 24"] is closed.*, **
4
- Only required to be met in OPERATIONAL CONDITIONS 1, 2 and 3.
- Not required to be met when the primary containment purge valves are open
.forlinerting, deinerting, pressure control, ALARA or air quality considerations for personnel entry, or Surveillances that require these valves
'to.be open.
LIMERICK - UNIT 1 3/4 6-11 Amendment No. !!),130 a.
CONTAINMENT SYSTEMS BASES 3/4.6.1.5 PRIMARY CONTAINMENT STRUCTURAL INTEGRITY This limitation ensures tNat the structural integrity of the containment will be maintained comparable to the original design standards for the life of the unit. Structural integrity is required to ensure that the containment will i
withstand the maximum calculated pressure in the event of a LOCA. A visual i
inspection in accordance with the Primary Containment Leakage Rate Testing i
Program is sufficient to demonstrate this capability.
i 3/4.6.1.6 DRYWELL AND SUPPRESSION CHAMBER INTERNAL PRESSURE The limitations on drywell and suppression chamber internal pressure ensure that the' calculated containment peak pressure does not exceed the design i
i pressure of 55 psig during LOCA conditions or that the external pressure differ-ential does not exceed the design maximum external pressure differential of i
5.0 psid.
The limit of - 1.0 to + 2.0 psig for initial containment pressure
-will limit the total pressure to s 44 psig which is less than the design
. pressure and is consistent with the safety analysis.
3/4.6.1.7 DRYWELL AVERAGE AIR TEMPERATURE i
The limitation on drywell average air temperature ensures that the con-tainment peak air temperature does not exceed the design temperature of 340*F during steam line break cond.itions and is consistent with the safety analysis.
I 3/4.6.1.8 DRYWELL AND SUPPRESSION CHAMBER PURGE SYSTEM The drywell and suppression chamber purge supply and exhaust. isolation valves are required to be closed during plant operation except as required for 4
inerting, deinerting, pressure control, ALARA or air quality considerations for personnel entry, or Surveillances that require the valves to be open.. Limiting the use of the drywell and suppression chamber purge system to specific criteria is imposed to protect the integrity of the SGTS filters. Analysis indicates that should a LOCA occur while this pathway is being utilized, the associated pressure surge through the (18 or 24") purge lines will adversely affect the integrity of SGTS. This condition is not imposed on.the 1 and 2 inch valves used
.for pressure control since a surge through these lines does not threaten the operability of SGTS.
4 Surveillance requirement 4.6.1.8 ensures that the primary containment pur valves are closed as required or, if open, open for an allowable reason. geIf a purge valve is open in violation of this SR, the valve is considered inoperable.
The SR is modified by a Note stating that primary containment purge valves are only required to be closed in OPERATIONAL CONDITIONS 1, 2 and 3.
The SR -
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is also modified by a Note stating that the SR ir not required to be met when i
.the purge valves are open for the stated reasons. The Note states that these valves may be opened for inerting, deinerting, pressure control, ALARA or air quality considerations for personnel entry, or Surveillances that require the valves to be open. The 18 or 24 inch purge valves are capable of closing in the environment following a LOCA.
Therefore, these valves are allowed to be open for limited periods of time.
The 31 day Frequency is consistent with other PCIV requirements.
LIMERICK - UNIT I B 3/4 6-2 Amendment No. 29, f06, ffs, ff5,130
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NUCLEAR REGULATORY COMMISSION WAsMINGToN, D.C. 200SH001 PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-353 LIMERICK GENERATING STATION. UNIT 2 i
AMENDMENT TO FACILITY OPERATING LICENSE i
i Amendment No.91 License No. NPF-85 1.
The Nuclear Regulatory Commission (the Commission) has found that:
~~~
A.
The application for amendment by Philadelphia Electric Company (the licensee) dated March 24,1997, as supplemented September 4,1998, 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.
P 4
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j 2-2.
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 Ucense No. NPF-85 is hereby amended to read as follows:
Technical Soecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 91, are hereby incorporated in the license. Philadelphia Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
~
3.
This license amendment is effective as of its date ofissuance, and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
%A f G, [y Robert A. Capra, Director Project Directorate 1-2 Division of Reactor Projects - t/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date ofissuance: October 1,1998 9
I 4
1 4
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ATTACHMENT TO LICENSE AMENDMENT NO. 91 FACILITY OPERATING LICENSE NO, NPF-85 DOCKET NO,50-353 i
Replace the following pages of the Appendix A Technical Specifications with the attached pages.
,The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove land 3/4611 3/4 411 B 3/4 6 2 B 3/4 & 2
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CONTAI,NMENT SYSTEMS DRYWELL AND SUPPRESSION CHAMBER PURGE SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.8 The drywell and suppression chamber purge system may be in operation with the supply and exhaust isolation valves in one supply line and one exhaust line open for inerting, deinerting, pressure control, ALARA or air quality considerations for personnel entry, or Surveillances that require the valves to be open.
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION:
With a drywell and/or suppression chamber purge supply and/or exhaust a.
isolation valve open, except as permitted above, close the valve (s) within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SVRVEILLANCE RE0VIREMENTS 4.6.1.8 At least once per 31 days, verify each primary containment purge valve [18" or 24") is closed.*, **
- Only required to be met in OPERATIONAL CONDITIONS 1, 2, and 3.
- Not required to be met when the primary containment purge valves are open for inerting, deinerting, pressure control, ALARA or air quality considerations for personnel entry, or Surveillances that require these valves to be open.
l LIMERICK - UNIT 2 3/4 6-11 Amendment No. 77, 91
-CONTAINMENT SYSTEMS 1
BASES 3 /4. 6.1. 5 PRIMARY CONTAINMENT STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment will be maintained comparable to the original design standards for the life of the unit. Structural integrity is required to ensure that the containment will withstand the maximum calculated pressure in the event of a LOCA. A visual inspection in accordance with the Primary Containment Leakage Rate Testing Program is sufficient to demonstrate this capability.
3/4.6.1.6 DRYWELL AND SUPPRESSION CHAMBER INTERNAL PRESSURE l
The limitations on drywell and suppression chamber internal pressure ensure that the calculated containment peak pressure does not exceed the design
. pressure of 55 psig during LOCA conditions or that the external pressure differ-i ential does not exceed the design maximum external pressure differential of 5.0 psid.
The limit of - 1.0 to + 2.0 psig for initial containment pressure 4
will limit the total pressure to s 44 psig which is less than the design l
. pressure and is consistent with the safety analysis.
1 3 /4. 6.1. 7 DRYWELL AVERAGE AIR TEMPERATURE-The limitation on drywell average air temperature ensures that the con-tainment peak air. temperature does not exceed the design temperature of 340'F during steam line break conditions and is consistent with the safety analysis.
i l
3/4.6.1.8 DRYWELL AND SUPPRESSION CHAMBER PURGE SYSTEM i
The drywell and suppression chamber purge supply and exhaust isolation valves are required to be closed during plant operation except as required for inerting, deinerting, pressure control, ALARA or air quality considerations for 4
personnel entry, or Surveillances that require the valves to be open. Limiting ~
the use of the drywell and suppression chamber' purge system to specific criteria is imposed to protect the integrity of the SGTS filters. Analysis indicates' that-should a LOCA occur while this pathway is being utilized, the associated
. pressure surge through the (18 or 24") purge lines will adversely affect the integrity of SGTS.
This condition is not imposed on.the 1 and 2 inch valves used for pressure control since a surge through these lines does not threaten the operability of SGTS.
Surveillance requirement 4.6.1.8 ensures that the primary containment purge valves are closed as required or, if open, open for an allowable reason.
If
,a purge valve is open in violation of this SR, the valve is considered inoperable.
The SR is modified by a Note stating that primary containment purge valves are only required to be closed in OPERATIONAL CONDITIONS 1, 2 and 3.
The SR-is also modified by a Note stating that the SR is not required to be met when the purge valves are open for the stated reasons. The Note states that these
. valves may be opened for inerting, deinerting, pressure control, ALARA or air quality considerations for personnel entry, or Surveillances that require the valves to be open. The 18 or 24 inch purge valves are capable of closing in the environment following a LOCA. Therefore, these valves are allowed to be open for limited periods of time. The 31 day Frequency is consistent with other PCIV requirements.
LIMERICK - UNIT 2 B 3/4 6-2 Amendment No. 51, 77, 81, 91 1