L-MT-11-077, Supplement to License Amendment Request: Revise Core Spray Pump Flow Rate in Specification 3.5.1 ECCS - Operating
| ML113570176 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 12/22/2011 |
| From: | O'Connor T Xcel Energy, Northern States Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| TAC ME5441, L-MT-11-077 | |
| Download: ML113570176 (5) | |
Text
/@ Xcel Energy December 22,201 1 Monticello Nuclear Generating Plant 2807 W County Road 75 Monticello. MN 55362 L-MT-11-077 10 CFR 50.90 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Monticello Nuclear Generating Plant Docket 50-263 Renewed Facility Operating License No. DPR-22 Supplement to License Amendment Request: Revise Core Sprav Pump Flow Rate in Specification 3.5.1, ECCS - Operating (TAC No. ME54411
Reference:
- 1)
Letter NSPM to NRC, "License Amendment Request: Revise Core Spray Pump Flow Rate in Specification 3.5.1, ECCS - Operating,"
(L-MT-11-015), dated February 7, 201 1.
On February 7, 201 1, the Northern States Power Company - a Minnesota Corporation (NSPM), submitted a license amendment request (Reference 1) for the Monticello Nuclear Generating Plant to revise the Core Spray pumps flow rate from 2800 to 2835 gallons per minute (gpm) within Surveillance Requirement (SR) 3.5.1.7, in Technical Specification (TS) 3.5.1, "ECCS - Operating." Reference 1 provided a draft marked-up copy of the affected TS page to the U.S. Nuclear Regulatory Commission (NRC) indicating the proposed change.
During a review by Monticello staff it was identified that Specification 3.5.2, "ECCS -
Shutdown," contained the exact same flow rate requirement as SR 3.5.1.7, and that the Core Spray pump flowrate specified in SR 3.5.2.4 should be revised accordingly. A revised SR 3.5.2.4 is provided in Enclosure I.
This change to SR 3.5.2.4 has the exact same technical basis as that for SR 3.5.1.7 and hence does not impact the technical content of the license amendment request. The change to this surveillance requirement has been discussed with the NRC Project Manager.
NSPM has reviewed the No Significant Hazards Consideration determination provided in Reference 1 for this license amendment request and determined that it is still applicable. The MNGP Plant Operations Review Committee reviewed the Core Spray pump flow rate value associated with this TS change. In accordance with 10 CFR 50.91, a copy of this change to the application, with the enclosure, is being provided to the designated Minnesota Official.
Document Control Desk L-MT-11-077 Page 2 of 2 Final retyped TS pages are not requested from a licensee by the NRC until near amendment issuance to ensure any intervening amendments are correctly reflected in the TS pages. The NRC Project Manager has indicated that this amendment is near issuance. Enclosure 1 provides retyped copies of the TS pages containing SR 3.5.1.7 and SR 3.5.2.4.
Summaw of Commitments This letter proposes no new commitments and does not revise any existing commitments.
Should you have questions regarding this letter, please contact Mr. Richard Loeffler at (763) 295-1247.
oing is true and correct.
lo Nuclear Generating Plant Enclosure cc:
Administrator, Region Ill, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC Minnesota Department of Commerce
ENCLOSURE 1 MONTICELLO NUCLEAR GENERATING PLANT REVISED AND RETYPED TECHNICAL SPECIFICATION PAGES FOR LICENSE AMENDMENT REQUEST: REVISE CORE SPRAY PUMP FLOW RATE IN SPECIFICATIONS 3.5.1 AND 3.5.2, ECCS - OPERATING AND ECCS - SHUTDOWN (2 pages follow)
ECCS - Operating 3.5.1 SR 3.5.1.7 Verify the following ECCS pumps develop the specified flow rate against a system head corresponding to the specified reactor to containment pressure.
SURVEILLANCE REQUIREMENTS (continued)
System Head Corresponding to a Reactor to No, of Containment Svstem Flow Rate Pumps Pressure of SURVEILLANCE Core Spray 22835 gpm 1
r 130 psi FREQUENCY LPCl 2 3870 gpm 1
2 20 psi SR 3.5.1.8
NOTE..............................
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.
Verify, with reactor steam dome pressure I 1025.3 psig and 2 950 psig, the HPC I pump can develop a flow rate 2 2700 gpm against a system head corresponding to reactor pressure.
NOTE..............................
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.
Verify, with reactor pressure I 165 psig, the HPCI pump can develop a flow rate r 2700 gpm against a system head corresponding to reactor pressure.
In accordance with the lnservice Testing Program In accordance with the lnservice Testing Program 24 months Monticello Amendment No. 446, 167
ECCS - Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE SR 3.5.2.2 Verify, for each required ECCS injectionlspray subsystem, the piping is filled with water from the pump discharge valve to the injection valve.
SR 3.5.2.3 Verify each required ECCS injectionlspray subsystem manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.
SR 3.5.2.4 Verify each required ECCS pump develops the specified flow rate against a system head corresponding to the specified reactor to containment pressure.
System Head Corresponding to a Reactor to No. of Containment Svstem Flow Rate Pumps Pressure of Core Spray 22835 gpm 1
1 130 psi LPCl 2 3870 gpm 1
2 20 psi SR 3.5.2.5
NOTE..............................
Vessel injectionlspray may be excluded.
Verify each required ECCS injectionlspray subsystem actuates on an actual or simulated automatic initiation signal.
FREQUENCY 31 days 31 days In accordance with the Inservice Testing Program 24 months Monticello Amendment No. 446, 167