ML043140110

Request for Additional Information to Modify the Basis of Technical Specification 2.4, Containment Cooling

ML043140110
Person / Time
Site:	Fort Calhoun
Issue date:	11/19/2004
From:	Wang A NRC/NRR/DLPM/LPD4
To:	Ridenoure R Omaha Public Power District
Wang A, NRR/DLPM, 415-1445
References
BL-03-001, TAC MC3217
Download: ML043140110 (4)

Text

November 19, 2004 Mr. R. T. Ridenoure Division Manager - Nuclear Operations Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.

Post Office Box 550 Fort Calhoun, NE 68023-0550

SUBJECT:

FORT CALHOUN STATION, UNIT NO. 1 - REQUEST FOR ADDITIONAL INFORMATION (TAC NO. MC3217)

Dear Mr. Ridenoure:

By letter dated May 21, 2004, Omaha Public Power District (OPPD) submitted an amendment request for the Fort Calhoun Station, Unit 1, to modify the Basis of Technical Specification 2.4, "Containment Cooling," to allow containment spray pumps to be secured during a loss-of-coolant accident to minimize the potential for containment sump clogging when certain conditions are met. The staff has completed its preliminary review of this submittal and has determined it needs additional information to complete the review. The staff's request for additional information is enclosed. This request was discussed with Thomas Byrne of your staff and it was agreed that a response would be provided within 30 days of receipt of this letter.

Sincerely,

/RA/

Alan B. Wang, Project Manager, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-285

Enclosure:

Request for Additional Information cc w/encl: See next page

November 19, 2004 Mr. R. T. Ridenoure Division Manager - Nuclear Operations Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.

Post Office Box 550 Fort Calhoun, NE 68023-0550

SUBJECT:

FORT CALHOUN STATION, UNIT NO. 1 - REQUEST FOR ADDITIONAL INFORMATION (TAC NO. MC3217)

Dear Mr. Ridenoure:

By letter dated May 21, 2004, Omaha Public Power District (OPPD) submitted an amendment request for the Fort Calhoun Station, Unit 1, to modify the Basis of Technical Specification 2.4, "Containment Cooling," to allow containment spray pumps to be secured during a loss-of-coolant accident to minimize the potential for containment sump clogging when certain conditions are met. The staff has completed its preliminary review of this submittal and has determined it needs additional information to complete the review. The staff's request for additional information is enclosed. This request was discussed with Thomas Byrne of your staff and it was agreed that a response would be provided within 30 days of receipt of this letter.

Sincerely,

/RA/

Alan B. Wang, Project Manager, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-285 DISTRIBUTION:

PUBLIC

Enclosure:

Request for Additional Information PDIV-2 Reading RidsNrrDlpmLpdiv (HBerkow) cc w/encl: See next page RidsNrrDlpmLpdiv2 (RGramm)

RidsNrrLAEPeyton RidsNrrPMAWang RidsOgcRp RidsAcrsAcnwMailCenter CJohnson (RidsRegion4MailCenter)

RLobel JBongarra ADAMS ACCESSION NO.: ML043140110 Nrr-088 OFFICE PDIV-2/PM PDIV-2/LA PDIV-2/SC NAME AWang:mp EPeyton RGramm DATE 11/19/04 11/15/04 11/19/04 OFFICIAL RECORD COPY

Ft. Calhoun Station, Unit 1 cc:

Winston & Strawn Mr. Daniel K. McGhee ATTN: James R. Curtiss, Esq. Bureau of Radiological Health 1400 L Street, N.W. Iowa Department of Public Health Washington, DC 20005-3502 401 SW 7th Street, Suite D Des Moines, IA 50309 Chairman Washington County Board of Supervisors Mr. Richard P. Clemens P.O. Box 466 Division Manager - Nuclear Assessments Blair, NE 68008 Omaha Public Power District Fort Calhoun Station Mr. John Hanna, Resident Inspector P.O. Box 550 U.S. Nuclear Regulatory Commission Fort Calhoun, NE 68023-0550 P.O. Box 310 Fort Calhoun, NE 68023 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Ms. Sue Semerera, Section Administrator Nebraska Health and Human Services Systems Division of Public Health Assurance Consumer Services Section 301 Cententiall Mall, South P.O. Box 95007 Lincoln, NE 68509-5007 Mr. David J. Bannister, Manager Fort Calhoun Station Omaha Public Power District Fort Calhoun Station FC-1-1 Plant P.O. Box 550 Fort Calhoun, NE 68023-0550 Mr. John B. Herman Manager - Nuclear Licensing Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.

P.O. Box 550 Fort Calhoun, NE 68023-0550

REQUEST FOR ADDITIONAL INFORMATION TECHNICAL SPECIFICATION 2.4 BASIS CHANGE OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT NO. 1 DOCKET NO. 50-285 NRC Bulletin 2003-01, "Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized Water Reactors," required that operators of pressurized water reactors (PWRs) state that the emergency core cooling systems (ECCS) and the containment spray (CS) recirculation functions meet applicable regulatory requirements with respect to adverse post-accident debris blockage or describe interim compensatory measures to reduce the risk associated with the potentially degraded or non-conforming ECCS and CS recirculation functions. By letter dated May 21, 2004, Omaha Public Power District (OPPD) submitted an amendment request for the Fort Calhoun Station, Unit 1 (FCS) as part of its commitment made to Bulletin 2003-01. OPPD proposed to modify the Basis of Technical Specification 2.4, "Containment Cooling," to allow CS pumps to be secured during a loss-of-coolant accident (LOCA) to minimize the potential for containment sump clogging when certain conditions are met. The staff has completed its preliminary review of this submittal and has determined it needs the following additional information to complete the review.

1. For the manual operator actions required to reduce to one train of CS operation, are all required actions taken from the main control room? Are there any actions required to be taken from the plant (i.e., from local control stations)? Describe the actions to reduce to one CS train.

2. Using ANSI/ANS 58.8 guidance, the analysis on page 7 of the May 24, 2004, submission indicates that the estimated time for operators to take all the required actions that terminate the CS pumps is approximately four minutes. The licensee further states that the emergency operating procedures do not direct these actions until other, more time restrictive actions such as post-trip actions, safety function status checks, or tripping of the reactor coolant pumps are performed. However, the required actions (i.e., to terminate the CS pumps) are intended to be taken as soon as possible and prior to the recirculation actuation signal (RAS). Is terminating to one CS train "time sensitive"? How much time is there from when operators complete the more time restrictive actions until the RAS is received? Does this time vary as a function of the LOCA size or is it constant? If the time is variable, what is the shortest amount of time that operators will have to successfully complete the actions to terminate one CS train (i.e., will operators have at least four minutes to complete the required actions under all LOCA conditions)?