ML20091L536
| ML20091L536 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 08/24/1995 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Philadelphia Electric Co |
| Shared Package | |
| ML20091L538 | List: |
| References | |
| NPF-39-A-100, NPF-85-A-064 NUDOCS 9508290236 | |
| Download: ML20091L536 (12) | |
Text
.
- 9%,.
l ge t
UNITED STATES 6
NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20eedWm01
%**e++)
PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-352 LIMERICK GENERATING STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.100 License No. NPF-39 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company (the licensee) dated August 31, 1994, as supplemented by letters dated May 11, and July 3, 1995, 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 i
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.
i 9508290236 950824 PDR ADOCK 05000352 P
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. 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.
100 are hereby incorporated into this 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 of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION r
Jo
- Stolz, Director Pr et Directorate I-2 Division of Reactor Projects - I/II Office ~of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 24, 1995
r o
ATTACHMENT TO LICENSE AMENDMENT NO.
FACILITY OPERATING LICENSE NO. NPF-39 DOCKET NO. 50-352 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 Insert X
X 3/4 3-110 3/4 3-110 3/4 3-111-B 3/4 3-7 8 3/4 3-7 i
9 1
i INDEX
[
l LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION E8&E i
i INSTRUMENTATION (Continued)
Table 3.3.7.9-1 Fire Detection Instrumentation............
3/4 3-93
~
i Loose-Part Detection System...............................
3/4 3-97 The information from pages 3/4 3-98
[
through 3/4 3-101 has been intentionally l
omitted. Refer to note on page 3/4 3-98..................
3/4 3-98 i
i Offgas Monitoring Instrumentation.........................
3/4 3-103 Table 3.3.7.12-1 offgas l
l Monitoring Instrumentation...............
3/4 3-104 Table 4.3.7.12-1 Offgas Monitoring Instrumentation Surveillance Requirements................
3/4 3-107 i
3/4.3.8 (Deleted) The information on pages 3/4 3-110 and 3/4 3-111 has been intentionally omitted.
t i
Refer to note on page 3/4 3-110.................
3/4 3-110 i
3/4.3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEtt ACTUATION l
INSTRUMENTATION.......................................
3/4 3-112 i
Table 3.3.9-1 Feedwater/ Main Turbine Trip System Actuation Instrumentation.........
3/4 3-113 Table 3.3.9-2 Feedwater/ Main Turbine Trip System Actuation Instrumen-l tation Setpoints.........................
3/4 3-114 i
I' Table 4.3.9.1-1 Feedwater/ Main Turbine Trip i
System Actuation Instrumenta-tion Surveillance Require-ments.....................................
3/4 3-115 4
3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1
. RECIRCULATION SYSTEM j
Rec i rc ul a t i on Loop s.......................................
3/4 4-1 a
l i
p i
i Amendment No. IS, 100 LIMERICK - UNIT 1 x
i
~
w-
'Section 3/4.3.8 (Deleted) p p
1 P
d -
4 i
1 THE INFORMATION FROM THIS TECHNICAL 4
SPECIFICATIONS SECTION HAS BEEN RELOCATED TO THE UFSAR.
TECHNICAL SPECIFICATIONS PAGE 3/4 3-111 3
j HAS BEEN INTENTIONALLY UNITTED.
l 4
J i
4 I
a
^""*"'**1*
LIMERICK. UNIT 1 3/4 3-110
INSTRUMENTATION BASES FIRE DETECTION INSTRUMENTATION (Continued)
The loss of detection capability for fire suppression systems, actuated by fire detectors, represents a significant degradation of fire protection for any area. As a result, the establishment of a fire watch patrol must be initi-ated at an earlier stage than would be warranted for the loss of detectors that provide only early fire warning. The establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to OPERABILITY.
The surveillance requirements for demonstrating the OPERABILITY of the fire detectors are based on the recommendations of NFPA 72E - 1990 Edition.
3/4.3.7.10 LOOSE PART DETECTION SYSTEM The OPERABILITY of the loose-part detection system ensures that sufficient capability is available to detect loose metallic parts in the primary system and avoid or mitigate damage to primary system components.
The allowable out-of-service times and surveillance requirements are consistent with the recom-mendations of Regulatory Guide 1.133, " Loose-Part Detection Program for the Primary System of Light-Water-cooled Reactors," May 1981.
3/4.3.7.11 (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE ODCM.
3 /4. '). 7.12 0FFGAS MONITORING INSTRUMENTATION,
Thi. instrumentation includes provisions for monitoring the concentr:. ions of potentially explosive gas mixtures and noble gases in the off-gas system.
3/4.3.8 (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE UFSAR.
3/4.3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION The feedwater/ main turbine trip' system actuation instrumentation is provided to initiate action of the feedwater system / main turbine trip system in the event of failure of feedwater controller under maximum demand.
LIMERICK - UNIT 1 B 3/4 3-7 Amendment No. 33, 48, 70, 100
em4 ne '
t UNITED STATES Y
E NUCLEAR REGULATORY COMMISSION U
I WASHINGTON, D.C. 20086 4 001 gs,...../
PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-353 LIMERICK GENERATING STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.64 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 August 31, 1994, as supplemented by letters dated May 11, and July 3, 1995, 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 rule,s 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.
i J
l.
. 2 1
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, i
and paragraph 2.C.(2) of Facility Operating License No. NPF-85 is hereby amended to read as follows:
~
l 4
Technical Specifications The. Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.
64, are hereby incorporated into this license.
Philadelphia Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
l 3.
This license amendment is effective as of its date of issuance and shall i
be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
(
Jc. n T. Stolz, Directot/
4 Pro'ect Directorate I-2 l
Di sion of Reactor Projects - I/II Office of Nuclear Reactor Regulation 2
Attachment:
i Changes to the Technical Specifications i
Date of Issuance: August 24, 1995 r
i i
l
l 1
I l
ATTACHMENT TO LICENSE AMENDMENT NO.
FACILITY OPERATING LICENSE NO. NPF-85 DOCKET NO. 50-353 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identiftad by Amendment number and contain vertical lines indicating the area of change.
Remove Insert X
X 3/4 3-110 3/4 3-110 3/4 3-111 B 3/4 3-7 B 3/4 3-7 O'
r l
I i
l IlfDil
~
LINITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS l
l SECTION ggg INSTRUMENTATION (Continued)
['
Table 3.3.7.9. Fire Detection Instrumentation............
3/4 3-93 Loose-Part Detection System...............................
3/4 3-97 i
The information from pages 3/4 3-98 through 3/4 3-101 has been intentionally l
omitted. Refer to note on page 3/4 3-98..................
3/4 3-98 l
Offgas Monitoring Instrumentation.........................
3/4 3-103 i
Table 3.3.7.12-1 Offgas l
Monitoring Instrumentation...............
3/4 3-104 l
i Table 4.3.7.12-1 Offgas Monitoring Instrumentation Surveill ance Requirements................
3/4 3-107.
3/4.3.8 (Deleted) The information on pages 3/4 3-110 and 3/4 3-111 has been intentionally omitted.
Refer to note on page 3/4 3-110.................
3/4 3-110 i
3/4.3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION..................:....................
3/4 3-112 l
Table 3.3.9-1 Feedwater/ Main Turbine Trip System Actuation Instrumentation.........
3/4 3-113 l
Table 3.3.9-2 Feedwater/ Main Turbine Trip System Actuation Instrumen-tation Setpoints.........................
3/4 3-114 j
Table 4.3.9.1-1 Feedwater/ Main Turbine Trip System Actuation Instrumenta-tion Surveillance Require-
)
ments.....................................
3/4 3-115 3/4.4 REACTOR C00UUIT SYSTEM 3
3/4.4.1 RECIRCULATION SYSTEM Recirculation Loops.......................................
3/4 4-1 2
i i
l i
I i
I LIMERICK - UNIT 2 x
Amendment No. II, 64 i
\\
i
l Sectitn 3/4.3.8.-(Deleted) t b
R i
THE INFORMATION FROM THIS TECHNICAL SPECIFICATIONS SECTION HAS BEEN RELOCATD TO THE UFSAR.
TECHNICAL SPECIFICATIONS PAGE 3/4 3-111 HAS BEEN INTENTIONALLY OMITTED.
l Amendment No. 64 LIMERICK'- UNIT 2 3/4 3 110
l INSTRUMENTATION BASES 3/4.3.7.9 FIRE DETECTION INSTRUMENTATION (Continued)
The loss of detection capability for fire suppression systems, actuated by fire detectors, represents a significant degradation of fire protection for any area. As a result, the establishment of a fire watch patrol must be initi-1 ated at an earlier stage than would be warranted for the loss of detectors that provide only early fire warning. The establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to OPERABILITY.
The surveillance requirements for demonstrating the OPERABILITY of the fire detectors are based on the recommendations of NFPA 72E - 1990 Edition.
3/4.3.7.10 LOOSE PART DETECTION SYSTEM The OPERABILITY of the loose-part detection system ensures that sufficient capability is available to detect loose metallic parts in the primary system and avoid or mitigate damage to primary system components. The allowable out-of-service times and surveillance requirements are consistent with the recom-mendations of Regulatory Guide 1.133, " Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors," May 1981.
3/4.3.7.11 (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE ODCM.
1 I
3/4.3.7.12 0FFGAS MONITORING INSTRUMENTATION,
This instrumentation includes provisions for monitoring the concentrations of potentially explosive gas mixtures and noble gases in the off-gas system.
3/4.3.8 (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE UFSAR.
3/4.3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION The feedwater/ main turbine trip system actuation instrumentation is provided to initiate action of the feedwater system / main turbine trip system in the event of failure of feedwater controller under maximum demand.
LIMERICK - UNIT 2 B 3/4 3-7 Amendment No. YI, 25, 33, 64