ML023570343

From kanterella
Jump to navigation Jump to search

Correction to Safety Evaluation for Amendment No. 130
ML023570343
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 01/07/2003
From: Hood D
NRC/NRR/DLPM/LPD3
To: Forbes J
Nuclear Management Co
References
TAC MB3706
Download: ML023570343 (4)


Text

January 7, 2003 Mr. Jeffrey S. Forbes Site Vice President Monticello Nuclear Generating Plant Nuclear Management Company, LLC 2807 West County Road 75 Monticello, MN 55362-9637

SUBJECT:

MONTICELLO NUCLEAR GENERATING PLANT - CORRECTION TO SAFETY EVALUATION FOR AMENDMENT NO. 130 (TAC NO. MB3706)

Dear Mr. Forbes:

On September 23, 2002, the Nuclear Regulatory Commission (NRC) issued Amendment No. 130 to Facility Operating License No. DPR-22 for the Monticello Nuclear Generating Plant.

The amendment consisted of changes to the Technical Specifications (TSs) in response to your application dated December 21, 2001, as supplemented April 26, 2002.

Item 3 on page 4 of the NRC staffs safety evaluation (SE) related to Amendment No. 130 contained a typographical error when describing the proposed change to TS 3.7.A.4.f.

Item 3 should have stated that if the requirements of current TS 3.7.A.4 cannot be met, the reactor shall be placed in "a Cold Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />," rather than "a Hot Shutdown condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />." Please replace the page 4 of the SE issued with Amendment No. 130 with the enclosed corrected page 4. This correction is consistent with your application, the TS pages issued with Amendment No. 130, and the NRC staffs intent.

Sincerely,

/RA/

Darl S. Hood, Senior Project Manager, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-263

Enclosure:

Corrected Page 4 of SE cc w/encl: See next page

ML023570343 OFFICE PDIII-1/PM PDIII-1/LA PDIII-1/SC NAME DHood RBouling LRaghavan DATE 01/07/03 12/30/02 01/07/03 Monticello Nuclear Generating Plant cc:

J. E. Silberg, Esquire Commissioner Shaw, Pittman, Potts and Trowbridge Minnesota Department of Commerce 2300 N Street, N. W. 121 Seventh Place East Washington, DC 20037 Suite 200 St. Paul, MN 55101-2145 U.S. Nuclear Regulatory Commission Resident Inspectors Office Adonis A. Neblett 2807 W. County Road 75 Assistant Attorney General Monticello, MN 55362 Office of the Attorney General 445 Minnesota Street Site Licensing Manager Suite 900 Monticello Nuclear Generating Plant St. Paul, MN 55101-2127 Nuclear Management Company, LLC 2807 West County Road 75 Mr. Roy A. Anderson Monticello, MN 55362-9637 Executive Vice President and Chief Nuclear Officer Robert Nelson, President Nuclear Management Company, LLC Minnesota Environmental Control 700 First Street Citizens Association (MECCA) Hudson, WI 54016 1051 South McKnight Road St. Paul, MN 55119 Nuclear Asset Manager Xcel Energy, Inc.

Commissioner 414 Nicollet Mall Minnesota Pollution Control Agency Minneapolis, MN 55401 520 Lafayette Road St. Paul, MN 55155-4194 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351 Commissioner Minnesota Department of Health 717 Delaware Street, S. E.

Minneapolis, MN 55440 Douglas M. Gruber, Auditor/Treasurer Wright County Government Center 10 NW Second Street Buffalo, MN 55313 March 2002

2) Add proposed TS 3.7.A.3.c, which states that if the requirements of CTS 3.7.A.3 cannot be met, the reactor shall be placed in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3) Add proposed TS 3.7.A.4.f, which states that if the requirements of CTS 3.7.A.4 cannot be met, the reactor shall be placed in a Cold Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and l
4) Renumber CTS 3.7.A.6 as proposed TS 3.7.A.5.d, and reword it to state that if the requirements of CTS 3.7.A.5 cannot be met, reduce Thermal Power to # 15-percent rated thermal power (RTP), within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, revise CTS 3.7.A.5.b to reflect when the containment shall be inerted and deinerted to conform to the new action statement, and change the title from Containment Atmosphere Control to Primary Containment Oxygen Concentration.

The licensee has revised the CTS Bases consistent with the changes described above.

Currently, CTS 3.7.A.2.a, 3.7.A.2.b and 3.7.A.2.c contain specific action statements which govern the time allowed before shutdown if LCOs are not met and specifies the time to shutdown. CTS 3.7.A.6 is an action statement which currently applies to all requirements of CTS 3.7.A and requires that the reactor be in cold shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if the requirements of CTS 3.7.A are not met. Therefore, CTS 3.7.A.2.a, 3.7.A.2.b and 3.7.A.2.c, together with 3.7.A.6, establish two separate and different action statements. In addition, using CTS 3.7.A.6 would allow certain systems required to be operable to be inoperable in Hot Shutdown when containment integrity is required. This overlap in TS applicability results in conflict and confusion on the part of operators as to which action statements are applicable. The proposed changes would resolve the overlap by providing specific action statements for CTS 3.7.A.1, 3.7.A.3, and 3.7.A.4 consistent with the LCO requirements specified for these sections in CTS 3.7.A.

The balance of this change would revise the wording of the CTS 3.7.A.6 action statement and renumbers it as proposed TS 3.7.A.5.d, which will make it specific to CTS 3.7.A.5. In addition, CTS 3.7.A.5.b would be revised to specify when containment shall be inerted and deinerted and change the title of CTS 3.7.A.5 to reflect the substance of this LCO. Inerting the primary containment is an operational problem because it prevents containment access without an appropriate breathing apparatus. Therefore, the primary containment is inerted as late as possible in plant startup and deinerted as soon as possible in plant shutdown. As long as reactor power is < 15-percent RTP, the potential for an event that generates significant hydrogen is low and the primary containment need not be inerted. Furthermore, the probability of an event that generates hydrogen occurring within the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of a startup or the last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before a shutdown is low enough to justify these windows, during which the primary containment is not inerted. The 24-hour time period is a reasonable amount of time to allow plant personnel to perform the containment atmosphere inerting or deinerting.

If oxygen concentration is $ 4.0 percent by volume at any time while operating, with the exception of the relaxations allowed during startup and shutdown, oxygen concentration must be restored to < 4.0 percent by volume within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The 24-hour completion time is allowed when oxygen concentration is $ 4.0 percent by volume because of the low probability and long duration of an event that would generate significant amounts of hydrogen occurring during this period. If oxygen concentration cannot be restored to within limits within the required Corrected by NRC letter dated January 7, 2003 l