ML20052E395

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Revises 820414 Response to IE Bulletin 80-04, Analysis of PWR Main Steam Line Break W/Continued Feedwater Addition. Correction to Figure 14.3.4-1 Caused Error in Response to Items 3 & 4.Revised Figure Encl
ML20052E395
Person / Time
Site: Point Beach  
Issue date: 05/04/1982
From: Fay C
WISCONSIN ELECTRIC POWER CO.
To: Clark R, Harold Denton
Office of Nuclear Reactor Regulation
References
REF-SSINS-6820 IEB-80-04, TAC-46851, TAC-46852, NUDOCS 8205110080
Download: ML20052E395 (3)


Text

Wisconsin Electnc mra courany 231 W. MICHICAN, P.O. BOX 2046, MILWAUKEE. WI 53201 May 4, 1982 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.

S. NUCLEAR REGULATORY COMMISSION 9

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Attention:

Mr.

R. A.

Clark, Chief

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Operuting Reactors, Branch 3

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DOCKET NOS. 50-266 AND 50-301

-A-IE BULLETIN NO. 80-04

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g POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 Ji /iu Our letter of April 14, 1982 provided additional information on IE Bulletin No. 80-04, Analysis of PWR Main Steam Line Break with Continued Feedwater Addition, as requested by your letter of February 26, 1982.

However, Figure 14.3.4-1 contained an error in the units presented on the ordinate axis.

The units should be 103 BTU /sec instead of 106 BTU /sec.

A corrected Figure 14.3.4-1 is attached hereto and will be included with the next Final Facility Description and Safety Analysis Report (FFDSAR) revision.

As a consequence of the foregoing, our response to the second set of questions, items 3 and 4, is revised as follows:

RESPONSE

Direct operator action is not required to prevent overpressurization of the containment.

As discussed in the Point Beach FFDSAR analysis for the main steam line break (MSLB), safety injection woufd be automatically initiated early in the transient as a result of low steam line pressure (Technical Specification setpoint is >500 psig), well in advance of the time where addition?1 feedwater flow becomes important.

Safety injection would also automatically initiate operation of the containment air recirculation fan coolers.

Following safety injection, the containment spray system will automatically come on when containment pressure reaches 25 psig.

Figure 14.3.4-1 j

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9 Mr. Harold R.

Denton May 4, 1932 of the Point Beach FFDSAR illustrates the heat removal capability of each of the four fan coolers.

As stated on page 6.3-3 of the Point Beach FFDSAR, each of the four fan-cooler units can remove heat at the rate of 13,900 BTU /sec (0.83 x 106 BTU / min) under saturated, air-steam, 60 psig conditions.

Also, on page 6.4-14 of the FFDSAR, it is stated that each of the two spray systems can remove 110 x 106 BTU /hr or 1.83 x 106 BTU / min.

Thus, the fan coolers and spray system together can remove the additional energy discharged into the containment by continued feedwater addition, at the conservatively large rate (4 x 106 BTU / min) mentioned above, for an indefinite period of time.

Operator action is not required to prevent containment pressure from exceeding its design value of 60 psig.

However, as stated in our April 25, 1980 letter, operational procedures call for isolation of the aaxiliary feed flow to the affected steam generator.

We regret any inconvenience which may have been caused by the incorrect figure and trust that the foregoing will clarify any confusion which may have resulted from its use.

Please give us a call if you have any questions regarding our responses to your questions.

Very truly yours, Cl '

s C. W.

Fay Assistant Vice President Enclosure Copy to NRC Resident Inspector i

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CONTAINMENT AIR RECIRCULATION FAN-COOLER REAT REMOVAL RATE AS A FUNCTION OF CONTAIhMTI ATMOSPHERE PRESSURE 20 ~~i

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FIGURE 14.3.4-1 (4-27-82)