ML19256G042

Submits Addl Info for NRC Review of Tech Spec Change 60 for Operation at Reduced Primary Sys Operating Pressure

ML19256G042
Person / Time
Site:	Point Beach
Issue date:	12/14/1979
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:	Harold Denton, Schwencer A Office of Nuclear Reactor Regulation
References
NUDOCS 7912270300
Download: ML19256G042 (5)

Text

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O Wisconsin Elecinc powca coursur 231 W. MICHIGAN, P.O. BOX 2046. MILWAUKEE, WI 53201 December 14, 1979 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. NUCLEAR REGULATORY COMMISSION Washington, D. C.

20555 Attention: Mr. A. Schwencer, Chief Operating Reactors Branch 1 Gentlemen:

DOCKET N05. 50-266 AND 50-301 TECHNICAL SPECIFICATION CHAtlGE Il0. 60 - ADDITIONAL INFORMATION OPERATION AT 2000 PSIA PRIMARY SYSTEM PRESSURE POINT BEACH tluCLEAR PLAtlT, UNITS 1 AtlD 2 By letter dated November 2,1979, Licensee filed a request for amendments to Facility Operating Licenses CPR-24 and DPR-27 to incorporate changes in the Technical Specifications to permit operation of the Point Beach Nuclear Plant, Units 1 and 2, at reduced primary system operating pressure.

During a telephone conversation with members of your Staff held on Noverrber 26, 1979, it was determined that certain additional information would be required to complete the Staff's safety review of this license amendment request.

As requested by your Staff, the following information is provided herewith :

1.

Provide a list of the kinetic characteristics used in the safety analysis, equivalent to that presented in Table 3.1 of WCAP-8151, " Fuel Densification, Point Beach duelear Plant Unit No. 2, Low Pressure Analysis", June 1973.

RESPONSE

Table 1 of Attachment A presents the requested information.

The values presented in Table 1 are also representative of those used for current reloads for both Unit 1 and Unit 2.

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Mr. Harold R. Denton, Director Deceaber 14, 1979 2.

Provide the end of cycle shutdown requirements and margins used in the safety analysis equivalent to Table 3.2 of WCAP-8151.

RESPONSE

Table 2 of Attachment A presents the.tquested information.

The values presented in Table 2 are applicable to both Ur.it 1 and Unit 2.

3.

Provide a list of the transiants which were reanalyzed for operation at 2000 psia primary system pressure.

RESPONSE

Table 3 of Attachment A presents a comparison of the transients reanalyzed for the current Technical Specification change versus these reanalyzed in WCAP-8151.

4.

Provide the justification for selecting the transients presented in the list of transients reanalyzed to cover operation at 2000 psia primary system pressure.

RESP 01SE:

The determination of which non-LOCA transients required re-analysis was based on the same rationale as that di';ussed in WCAP-8151. Section 4.3 of WCAP-8151 presents a discussion of the relevant considerations. A similar review of the effect of low pressure operation on each of the accidents analyzed in the Point Beach Final Facility Description and Safety Analysis Report (FFDSAR) led te the conclusion that only the indicated accidents need be reanalyzed for operation at 2000 psia primary system pressure, For all accidents, the conclusions of the FFDSAR remain valid at die reduced operating pressure.

We trust that the foregoing will satisfy your requirements.

Very truly yours,

C. W. Fay, Director Nuclear Power Department Attachment i643 099

Attachment A TABLE 1 POINT BEACII - UNIT 2 - CYCLE 5 KINETICS CHARACTERISTICS CYCLE 5 Moderator Temperature

-3.5 to O Coefficient (Ap/*F)

Moderator Density Coefficient 0.0 to 0.35 (Ap/gm/cc)

Doppler Coefficient

-2.5 to -1.0 (Ap/*F) x 105 Delayed Neutron Fraction 0.453 to 0.70 Seff (%)

Prompt Neutron Lifetime 20 (usec)

Maximum Reactivity 80 Withdrawal Rate (pcm/sec) 1643 100

TABLE 2 END OF CYCLE SHUTDOWN REQUIREMENTS AND MARGINS POINT BEACH UNIT 2, CYCLE 5 Item Control Rod Worth (%ao)

Cycle 5 All Rods Inserted

>8.20 All Rods Inserted Less Worst Stuck Rod

>7.10 (1) Less 10%

>6.40 Control Rod Requirements (%ao)

Reactivity Defects (Combined Doppler, 21 90 Tavg, Void and Redistribution Effects) 0 1

70 Rod Insertion Allowance 1

60 3

(2) Total Requirements Shutdown Margin ((l) - (2)] (%Ap)

>2.80 Required Shutdown Margin (%ap) 2.77 1643 101 F

TABLE 3 ACCIDENTS RE-ANALYZED FOR LOW PPISSURE OPERATION Current T/S WCAP-8151 Change Rod Ejection Rcd Ejection Loss of Flow Loss of Flow Locked Rotor Locked Rotor Rod Withdrawal at Power 1643 102