ML20137T081
| ML20137T081 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 04/10/1997 |
| From: | Sorensen J NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TAC-M96492, TAC-M96493, NUDOCS 9704150308 | |
| Download: ML20137T081 (2) | |
Text
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Northern states Power Company 1717 Wakonade Dr. E.
Welch, MN 55089 Telephone 612-388-1121 April 10,1997 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 4
PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Comments on Safety Evaluation Report Regarding Containment Coolina Systems (TAC Nos. M96492 and M96493) l Reference 1: Safety Evaluation by the Office of Nuclear Reactor Regulation Related to Amendment Nos.125 and 117 to Facility Operating License Nos.
DPR-42 and DPR-60, Northern States Power Compeay, Prairie Island Nuclear Generating Plant, Unit Nos.1 and 2, Docket Nos. 50-282 and 50-306, dated February 10,1997.
Northern States Power Company's (NSP) offers comments on the Safety Evaluation Report provided in Reference 1 as follows:
On page 1, the first sentence of the last paragraph which states, "During normal plant operation, fan coil units are supplied with chilled water supply to cool the containment." is correct for warm weather operations. During normal operation in cold weather, the fan coil units are supplied with cooling water to cool the containment.
The next sentence on page 1 which carries over to page 2, implies that the cooling water system supplies cooling water to the residual heat removal system heat exchangers. The residual heat removal system heat exchangers are cooled by the component cooling system which in turn is cooled by the cooling water system.
On page 2, the second sentence in the first paragraph under section 2.2, states that, "The licensee subsequently found that under post-accident conditions, system f
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USNRC +* 4/10/97 2 Pega 2 of 2 psessure would be so low that boiling could occur in the Unit 1 upper level fan e coolers." This statement is also true for Unit 2. s. j in the last paragraph on page 2, the parenthetical statement, "for at least 45 j minutes", implies that the containment spray system is required to be operated for p control room personnel dose mitigation for 45 minutes following a LOCA. The - analyses presented in the supporting License Amendment Request stated that the j containment spray system was assumed to operate for 45 minutes following a main i steam line break. The containment spray system would not be expected to operate. .for 45 minutes following a design basis large break LOCA since the Prairie Island i containment spray system is not operated following the injection phase, that is, j when the volume in the refueling water storage tank is depleted. Control room dose i analyses demonstrate that General Design Criterion 19 is met by operation of the containment spray system during the injection phase time period. If you have any questions related to this letter, please contact myself or Dale i Vincent at 612-388-1121. i Joel P. Sorensen Plant Manager, Prairie Island Nuclear Generating Plant c: Regional Administrator-lil, NRC NRR Project Manager, NRC Senior Resident inspector, NRC State of Minnesota Attn: Kris Sanda J E Silberg . =... -,. ._,4 _ ---}}