ML17164B052
| ML17164B052 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 05/25/1999 |
| From: | Bajwa S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17164B053 | List: |
| References | |
| NUDOCS 9906020022 | |
| Download: ML17164B052 (6) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 PPRL INC.
ALLEGHENYELECTRIC COOPERATIVE INC.
DOCKET NO. 50-387 SUS UEHANNASTEAM ELECTRIC STATION UNIT 1 AMENDMENTTO FACILITYOPERATING LICENSE Amendment No.
181 License No. NPF-14 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application for the amendment filed by PP8L, Inc., dated March 12, 1999, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facilitywilloperate in conformity with the application, the provisions of the Act, and the 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 willbe conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment willnot 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.
j 9906020022 990525 PDR ADOCK 05000387 P
I I
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 the Facility Operating License No. NPF-14 is hereby amended to read as follows:
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
181 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
PP8L 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 after startup from the Unit 1 eleventh refueling and inspection outage currently scheduled for spring 2000.
FOR THE NUCLEAR REGULATORYCOMMISSION S. Singh Bajwa, Chief, Section 1
Project Directorate I
Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
Nay 25, 1999
ATTACHMENTTO LICENSE AMENDMENTNO.
FACILITYOPERATING LICENSE NO. NPF-14 DOCKET NO. 50-387 Replace the following pages of the Appendix A Technical Specifications with attached revised pag'es.
The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
REMOVE 3.342 3.3-43 INSERT 3.3-42 3.3-43
ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 1 of 6)
Emergency Core Cooling System Instrunentation FUNCTION APPLICABLE NODES OR OTHER SPECIFIED CONDIT IONG REQUIRED CHANNELS PER FUNCTIOIL CONDITIONS REFERENCED FROH REQUIRED ACTION A.1 SURVEILLANCE REQUIREHENTS ALLOWABLE VALUE 1.
Core Spray System a.
Reactor Vessel Mater Level Low Low Low, Level 1
b.
Drywell Pressure High c.
Reactor Steam Dome Pressure - Low (initiation) 1,2,3, 4(a) 5(a) 1,2,3 1,2,3 4(a) 5(a) 4(b) 4(b)
SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1 '
SR 3.3.5.1.2 SR 3.3.5.1.'3 SR 3.3.5.1.5 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5
'a -136 inches s 1.88 psig a 407 psig (lower) s 433 psig (upper) d.
Reactor Steam Dome Pressure - Low (injection permissive) e.
Hanual Initiation 2.
Low.Pressure Coolant Injection (LPCI) System a.
Reactor Vessel Mater Level Low Low Low, Level 1
1,2,3 4(a) 5(a) 1 ~2i3I 4(a) 5(a) 1,2,3, 4(a) 5(a) 2 1 per subsystem 4(c)
SR 3.3.5.1.2 a 407 psig (lower)
SR 3.3.5.1.3 s 433 psig (upper)
SR 3.3.5.1.5 SR 3.3.5.1.2 a 407 psig (lower)
SR 3.3.5.'1.3
< 433 psig (upper)
SR 3.3.5.1.5 SR 3.3.5.1.5 NA B
> -136 inches SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 (continued)
(a)
When associated subsystem(s) are required to be OPERABLE.
(b)
Also required to initiate the associated diesel generator (DG), initiate Drywall Cooling Equipment Trip, and Emergency Service liater (ESW) Pump timer reset.
'c)
Also required to initiate the associated
I SUSQUEHANNA UNIT 1 TS / 3.3-42 Amendment No. $78, 181
ECCS Instrumentation 3.3.5.1 I
I Table 3.3.5.1-1 (page 2 of 6)
Emergency Core Cooling System Instrunentation FUNCTION APPLICABLE NODES OR OTHER SPECIFIED CONDITIONS REOUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROH REQUIRED ACTION A.1 SURVEILLANCE REOUIREHEHTS ALLOMABLE VALUE 2.
LPCI System (continued) b.
Drywell Pressure High c.
Reactor Steam Dome Pressure - Low (initiation) d.
Reactor Steam Dome Pressure Low (injection permissive) e.
Reactor Steam Dome Pressure Low (Recirculation Discharge Valve Permissive) 1,2,3 1,2,3 4(a) 5(a) 1,2,3 4(a) 5(a) 1(d) 2(d) 3(d)
SR 3.3.F 1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.'I.2 SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3 '.1.5.
SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.F 1.5 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 s 1.88 psig a 407 psig (lower) s 433 psig (upper) a 407 psig.(lower) s 433 psig'upper)
> 407 psig (lower)
< 433 psig (upper)
> 216 psig (continued)
(a)
When associated subsystem(s) are required to be OPERABLE.
(c)
Also required to initiate the associated
- Dgs, ESlJ pwp timer reset and Turbine Building and Reactor Building Chiller trip..
(d)
Mith either associated recirculation pmp discharge or bypass valves open.'USQUEHANNA
- UNIT 1 TS / 3.3-43 Amendment R.
I'78, 181