L-PI-07-099, Supplement to License Amendment Request (LAR) to Revise Technical Specification (TS) 3.5.3 Operability Requirements for Safety Injection (SI) Subsystem
| ML073470821 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 12/13/2007 |
| From: | Wadley M Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-PI-07-099, TAC MD4209, TAC MD4210 | |
| Download: ML073470821 (4) | |
Text
NMC>
Committed to Nuclear Excellet>ce DEC 1 3 2007 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Operated by Nuclear Management Company, LLC L-PI-07-099 10 CFR 50.90 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 License Nos. DPR-42 and DPR-60 Supplement to License Amendment Request (LAR) to Revise Technical Specification
/TS) 3.5.3 Operability Requirements for Safetv Injection (SI) Subsystem (TAC Nos.
MD4209 and MD4210)
Reference:
- 1. License Amendment Request (LAR) to Revise Technical Specification (TS) 3.5.3 Operability Requirements for Safety Injection (SI) Subsystem, dated January 29,2007, Accession Number ML070300113.
- 2.
Supplement to License Amendment Request (LAR) to Revise Technical Specification (TS) 3.5.3 Operability Requirements for Safety Injection (SI) Subsystem, dated November 19, 2007, Accession Number ML073240077.
In Reference 1, Nuclear Management Company, LLC (NMC) submitted an LAR for the Prairie Island Nuclear Generating Plant (PINGP) Units I and 2 to revise TS 3.5.3, "ECCS (Emergency Core Cooling Systems) - Shutdown operability requirements for the SI subsystem by addition of a Limiting Condition for Operation (LCO) Note.
Pursuant to telephone discussions with the NRC Staff, this supplement provides proposed Bases page B 3.5.3-2 (for information only) which has been revised as shown in Enclosure 1 and supersedes Bases page B 3.5.3-2 submitted in Reference 2. NMC submits this supplement in accordance with the provisions of 10 CFR 50.90.
The supplemental information provided in this letter does not impact the conclusions of the Determination of No Significant Hazards Consideration and Environmental Assessment presented in the January 29,2007 submittal and the November 19,2007 supplement.
In accordance with 10 CFR 50.91, NMC is notifying the State of Minnesota of this LAR by transmitting a copy of this letter and enclosure to the designated State Official.
171 7 Wakonade Drive East Welch, Minnesota 55089-9642 Telephone: 651.388.1 121
Document Control Desk Page 2 Please address any comments or questions regarding this LAR supplement to Mr. Dale Vincent, P.E., at 651-388-1 121.
Summaw of Commitments This letter contains no new commitments and no revisions to existing commitments.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on QEC 1 3 2009
~,.Uxl"-y Michael D. Wadley Site Vice president, Prairie Island Nuclear Generating Plant Units 1 and 2 Nuclear Management Company, LLC Enclosures (1) cc:
Administrator, Region Ill, USNRC Project Manager, Prairie Island, USNRC Resident Inspector, Prairie Island, USNRC State of Minnesota
ENCLOSURE Bases Pages (Markup)
(For Information Only) 1 page follows
ECCS - Shutdown B 3.5.3 BASES (continued)
In MODE 4, one of the two independent (and redundant) ECCS trains is required to be OPERABLE to ensure that sufficient ECCS flow is available to the core following a DBA.
In MODE 4, an ECCS train consists of an SI subsystem and an RHR subsystem. Each train includes the piping, instruments, and controls to ensure an OPERABLE flow path capable of taking suction from the RWST and transferring suction to the containment sump.
During an event requiring ECCS actuation, a flow path is required to provide an abundant supply of water from the RWST to the RCS via the SI subsystem capable [through manual actions) of injecting into each of the cold leg injection nozzles and reactor vessel upper plenum nozzles. In the long term, a flow path is required to provide recirculation flow via the RHR subsystem from the containment sump into each of the reactor vessel upper plenum nozzles.
This LC0 is modified by 1- --
Notes. Note 1 Wallows an RHR train to be considered OPERABLE during alignment and operation for decay heat removal, if capable of being manually realigned (remote or local) to the ECCS mode of operation and not otherwise inoperable. This allows operation in the RHR mode during MODE 4.
Note 2 allows an S1 train to be considered OPERABLEkn-the piimp is capable of being; manually started lbr__E_CCS iniectionkom thc contr-0-1 room.
APPLICABILITY In MODES 1,2, and 3, the OPERABILITY requirements for ECCS are covered by LC0 3.5.2.
In MODE 4 with RCS temperature below 350°F and both RCS cold leg temperatures above the SI pump disable temperature specified in the PTLR, one OPERABLE ECCS train is acceptable without single failure consideration, on the basis of the stable reactivity of the Prairie Island Units 1 and 2 Unit 1 - Revision 4-86 Unit 2 - Revision 4-86