ML20097D189

Provides Clarification of 951213 Changes to TS SR 4.5.2.h Re Min & Max Flow Requirements for Centrifugal Charging & SI Pumps

ML20097D189
Person / Time
Site:	Wolf Creek
Issue date:	02/05/1996
From:	Maynard O WOLF CREEK NUCLEAR OPERATING CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
WO-96-0018, WO-96-18, NUDOCS 9602120235
Download: ML20097D189 (4)

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• b WFLF CREEK NUCLEAR OPERATING CORPORATION Otto L. Maynard Vice President Plant operations February 5, 1996 WO 96-0018 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-137 Washington, D. C. 20555 l

Reference:

Letter WO 95-0179 dated December 13, 1995, from O. L. Maynard, WCNOC, to USNRC

Subject:

Docket No. 50-482: Clarification of' Changes to Technical Specification Surveillance Requirement 4.5.2.h.

Gentlemen:

This letter provides clarification of information submitted by the Reference in an application for amendment to Facility Operating License No. NPF-42 for Wolf Creek Generating Station (WCGS). This license amendment request proposed '

revising the minimum and maximum flow requirements for the centrifugal charging and safety injection pumps specified in Technical Specification Surveillance Requirement 4.5.2.h. This additional- information is being

. submitted, in response to conversations on January 24, 1996, with the NRC Project Manager for WCGS, to clarify the impact of the proposed changes to the emergency core cooling system (ECCS) flow surveillance requirements for the small break loss of coolant accident (LOCA) analysis.,

Table 1, which was provided in the Reference, compared the current and the proposed Technical Specification minimum flow requirements for the Centrifugal Charging Pumps (CCPs) and Safety Injection Pumps (SIPS). The table represented the calculated flowrate (at RCS pressure = 0 psig) actually used in the small break and large break LOCA analyses. This table should be revised to reflect both LOCA analyses as follows.

Table 1 PUMP Tech Spec Minimum Requirements Flowrate assumed Current Value Proposed Value in SB/LB LOCA(gpm) l CCP 346 330 326.85 SI 459 450 444.82

• Sum of injection flowrates for the (3) intact loops.

9602120235 960205 ADOCK 05000482 90 PDR .

P PDR g g PO. Box 411/ Burlington, KS 66839 / Phone: (316) 364-8831 An Equal Opportunsty Ernployer M T/HC/ VET

i WO 96-0018 Page 2 of 2 The title previously presented in the fourth column of Table 1, "Flowrate assumed in LB LOCA," was incorrectly labeled because these flowrates were used in both the large break LOCA analysis and small break LOCA analysis. The flowrate values indicated above (326.85 gpm for the CCP and 444.82 gpm for the SIP) represent the flow that is expected to be provided by the operating CCP or SIP to the core via the three intact RCS loops when the RCS depressurizes to o psig. These flowrate values were used in the model that simulated the performance of the CCP and SIP for the large break LOCA analysis as well as the small break LOCA analysis. The ECCS flowrates used in the small break and large break LOCA analyses are expressed as a function of RCS pressure. These ECCS flowrates were calculated based on the same ' referenced flowrate which corresponds to an RCS pressure of 0 psig. In other words, the calculated ECCS flowrates contributed by the CCP and SIP (see the attached figure) used in the small break LOCA and large break LOCA are the same.

The ECCS flow calculations are based upon the flowrates (corresponding to an RCS pressure of 0 psig) that are more limiting than the surveillance requirements acceptance criteria for minimum flow limits for the CCP and the SIP. With the implementation of the proposed changes, the CCP and SIP flows following a postulated small break (or large break) LOCA, are still expected to be higher than that uced in the small break (or large break) LOCA analysis.

Therefore, implementation of the proposed changes of the ECCS flow surveillance requirements with respect to the minimum flow for the CCP and SIP would have no impact on the calculated peak cladding temperatures for the spectrum of small breaks or large breaks considered in the current licensing basjs.

In ancordance with 10 CFR 50.91, a copy of this information, with the attachreent , is being provided to the designated Kansas State official.

If you have any questions concerning this matter, please contact me at (316) 364-8831, extension 4450, or Mr. Richard D. Flannigan, at extension 4500.

Very truly yours, O.

UlW ' /ayd Otto L. Maynard OLM/jra Attachment cc: G. W. Allen (KDHE), w/a L. J. Callan (NRC), w/a W. D. Johnson (NRC), w/a J. F. Ringwald (NRC) , w/a J. C. Stone (NRC), w/a l

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STATE OF KANSAS ')

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COUNTY OF COFFEY.. )

Otto L. Maynard,' of lawful age, being first duly sworn upon oath says that he is Vice President Plant Operations of Wolf Creek Nuclear Operating Corporation; that he has read the foregoing document and knows the content thereof; that he has executed that same for and on behalf of said Corporation with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.

L By f/////// d//JuY OttY L. MKynard /

Vice President Plant Operations SUBSCRIBED and sworn to before me this .5 day of R8 , 1996.

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Notary Public ]

Expiration Date IS/O9 I999 i

I MARY E. GIFFORD Notary Public. State of Kansas

.My Appt. Expires e

s e Attachment to WO 96-0018 .

Page 1 of 1 -v-4 CCP/ SIP Flowrates Used in the Licensing Basis  :

Large-Break LOCA and Small-Break LOCA Analyses 4 5 0 : : -444.82

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