ML20206A503
| ML20206A503 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 04/23/1999 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20206A500 | List: |
| References | |
| NUDOCS 9904280191 | |
| Download: ML20206A503 (4) | |
Text
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UNITED STATES s
NUCLEAR REGULATORY COMMISSION WAsNINGToN, D.C. SOOOS GOM
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.189 TO FACILITY OPERATING LICENSE NO. DPR-24 AND AMENDMENT NO.194 TO FACILITY OPERATING LICENSE NO. DPR-27 WISCONSIN ELECTRIC POWER COMPANY POINT BEACH NUCLEAR PLANT. UNITS 1 AND 2 DOCKET NOS. 50-266 AND 50-301
1.0 INTRODUCTION
By [[letter::L-98-431, Application for Amends to Licenses DPR-24 & DPR-27,modifying TS to Provide Specific Numerical Setting for Rt,Rcp Trip & AFW Initiation on Loss of Power to 4 Kv Buses.Rev 1 to Calculation 9334281-01 Re RCP Internal Voltage Decay,Encl|letter dated May 28,1998]], as supplemented with additional information in letter dated December 11,1998, the Wisconsin Electric Power Company (the licensee) requested amendments to the Technical Specifications (TS) appended to Facility Operating License No. DPR-24 for Point Beach Nuclear Plant, Unit 1, and Facility Operating License No. DPR-27 for Point Beach Nuclear Plant, Unit 2. The proposed amendments would change the TS to provide specific numerical setpoint limits for reactor trip, reactor coolant pump trip and auxiliary feedwater initiation on loss of power to the 4 kV buses.
The application also requests bases changes to properly reflect reactor operating restrictions with less than two reactor coolant pumps operating. These changes are consistent with prrviously approved Amendmsnt 178 (Unit 1) and Amendment 182 (Unit 2).
The additional information provided by the December 11,1998, letter provided additional clarifying information and did not affect the staff's initial determination of no significant hazards consideration.
2.0 EVALUATION 2.1 Undervoltaae Setooint Limits The licensee proposed to delete "a75 percent of normal voltage" and substitute "a3120 volts" for the undervoltage relay limiting safety system settings for the undervoltage reactor trip protection function (Specification 15.2.3 (6)), the reactor coolant pump motor breaker function (Specification 15.2.3 (8) (b)), and the auxiliary feedwater initiation function (Specification 15.3.5-1 item 8). The purpose of these proposed changes is to provide a specific numerical value, "3120 volts," for the settings instead of a settings based on a percentage of a non-specific term, " normal voltage," which can cause confusion since the term is not defined in the TS.
9904290191 990423 PDR ADOCK 05000266 Y
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Since " normal" or " nominal" voltage for a 4 kV system is typically understood to be 4160 V and 75% of that would be 3120 V, the staff views the proposed changes as mainly editorialin nature and finds them acceptable on that basis, 1
During discussions pertaining to the background information related to these changes, the licensee stated that calculations supporting the selection of the proposed numericallimiting safety system settings were updated taking the effects of voltage decay, equipment response times, and instrumentation errors into account. Although the proposed changes to the TS were considered to be editorial as stated above, the staff reviewed the supporting calculations (Sargent & Lundy Calculation No. 93334281.01 and Duke Engineering & Services cat.C No. PBNP-lC-33) and found them to be conservative.
2.2 Chanaes to Bases The BASES presently state:
Sustained operation with only one pump will not be permitted above 3.5 percent power. If a pump is lost while operating between 3.5 percent and 50 percent power, an orderly and immediate reduction in power level to below 3.5 percent is allowed. The power-to-flow ratio will be maintained equal to or less than unity, which ensures that the minimum DNB ratio increases at lower flow because the maximum enthalpy rise does not increase above the maximum enthalpy rise which occurs during full power and full flow operation.
This would be changed to read:
Sustained power operation is not permitted with only one reactor coolant pump. If a pump is lost while operating below 50 percent power, an orderly shutdown is allowed. The power-to-flow ratio will be maintained equal to or less than unity, which ensures that the minimum DNB ratio increases at lower flow because the maximum enthalpy rise does not increase above the maximum enthalpy rise which occurs during full power and full flow operation.
These changes are consistent with previously approved Amendment 178 (Unit 1) and Amendment 182 (Unit 2). Current safety analyses for the loss of reactor coolant flow event when power is greater than 50%, assume that both reactor coolant pumps are initially operating and failure of either pump will cause a reactor trip. If. actor power is less than 50%, and one reactor coolant pump is lost, an orderly shutdown is permitted, no reactor trip being necessary.
The proposed bases changes are necessary to properly reflect these features.
Bases page 15.2.3-7 was also changed to reflect a revision to the Final Safety Analysis j
Report (FSAR). Reference 6 reflects this change by replacing FSAR Section 7.3 with i
Section 7.7 1
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3.0 STATE CONSULTATION
in accordance with the Commission's regulations, the Wisconsin State official was notified of the proposed issuance of the amendments. The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
These amendments change a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The staff has determined that the amendments involve no significant increase in the amounts, and no signmcant change in the types, of any effluent that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously published a proposed finding that these amendments involve no significant hazards consideration and there has been no public comment on such finding (63 FR 38198). Accordingly, these amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental
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impact statement or environmental assessment need be prepared in connection with the issuance of these amendrnents.
5.0 CONOLUSION The Commission has concluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuanco of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: F. Burrows Date: April 23, 1999
April 23, 1999 Mr. Michael B. Sellman.
Senior Vice President and Chief Nuclear Officer Wisconsin Electric Power Company 231 West Michigan Street i
Milwaukee, Wl. 53201 i
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 -ISSUANCE OF-AMENDMENTS RE: TECHNICAL SPECIFICATIONS REQUIREMENTS FOR i
4KV UNDERVOLTAGE TRIP SETPOINTS (TAC NOS. MA2078 AND MA2079)
Dear Mr. Sellman:
i The Commission has issued the enclosed Amendment No.189 to Facility Operating License No. DPR-24 and Amendment No. 194 to Facility Operating License No. DPR-27 for the Point Beach Nuclear Plant, Units 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TS) in response to your application dated May 28,1998, as supplemented by additional information in your letter dated December 11,1998.
These amendments change the TS to provide specific numerical setpoint limits for reactor trip, reactor coolant pump trip, and auxiliary feedwater initiation on loss of power to the 4 kV buses.
A copy of our related Safety Evaluation is also enclosed. The notice of issuance will be included j
in the Commission's biweekly FederalRegisternotice.
l Sincerely, Original signed by:
Beth A. Wetzel, Senior Project Manager, Section 1 Project Directorate 111 Division of Licensing Project Management Office of Nuclear Reactor Regulation i
Docket Nos 50-266 and 50-301
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Enclosures:
- 1. Amendment No.189 to DPR-24
- 2. Amendment No.194 to DPR-27
- 3. Safety Evaluation cc w/encis:
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