ML20081H050
| ML20081H050 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/17/1995 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20081H049 | List: |
| References | |
| NUDOCS 9503240077 | |
| Download: ML20081H050 (4) | |
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-UNITED STATES NUCLEAR REGULATORY COMMISSION i
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%,**,,4 SAFETY EVALUATION BY THE'0FFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.106 TO FACILITY OPERATING LICENSE NO.'NPF-49 i
NORTHEAST NUCLEAR ENERGY COMPANY. ET AL.
MILLSTONE NUCLEAR POWER STATION. UNIT NO. 3-DOCKET NO. 50-423 1
1.0 INTRODUCTION
By letter dated August 4, 1994, the Northeast Nuclear Energy Company (NNEC0/the licensee) submitted a request for changes to.the Millstone Nuclear j
' Power Station, Unit No. 3 Technical Specifications. (TS). The requested i
changes would change TSs 3.4.2.1 and 3.4.2.2 and Table 3.7-3, and involve relaxing the setpoint tolerance for the pressurizer safety valves (PSVs) and 1
the main steam safety valves (MSSVs) from fl% to i3%. The requested changes J
.are supported by the licensee's Cycle 4 Reload analysis.
j 2.0 EVALUATION Overpressure protection for the reactor coolant system (RCS) and the main I
steam system is provided, in part, by the_ PSVs and the MSSVs located on the pressurizer and on the four main steam lines, respectively. The current TS requires one PSV to be operable in Mode 4 and all PSVs are required operable in Modes 1, 2, and 3 with a lift setting of 2500 psia il%. All of the MSSVs i
are required operable during Modes 1, 2 and 3 with lift settings in increments of 10 psig, ranging.from 1185 psig to 1225 psig, i1%.
By letter. dated November 1,1990, NNECO submitted proposed TS changes and a.
reload analysis specific to the Millstone, Unit 3' Cycle 4 Reload. The reload analysis incorporated the VANTAGE 5 Hybrid (5H) fuel design and also examined for-the the impact on the' safety analysis of the increase in the setpoint tolerance for the PSVs and MSSVs from fl% to 13%.
The TS changes proposed by the current submittal are supported by the licensee's Cycle 4 Reload analysis, which was approved by the staff on March 11, 1991.
The November 1990 analysis for the non-loss of coolant accident (non-LOCA) transients included revisions in the modeling of the PSVs and MSSVs. The licensee included the following in the analysis: (1) a 3% accumulation and a 3% setpoint drift; (2) the pressurizer pressure was allowed to reach full rated flow over the range of 2575 to 2652 psia; and (3) the steam generator pressure was allowed to reach 1320 psia - 110% of the steam generator design i
pressure.
The licensee also indicated that the LOCA analyses considered the 1
3% MSSV drift from the setpoint for both the large and small break LOCA analyses, and the analyses remained bounding.
9503240077 950317' ADOCK O gDR
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To support a future request to relax the setpoint of the PSVs and MSSVs from fl% to i3%, the licensee reanalyzed the increase in the PSV and MSSV setpoint tolerance in their November 1990, Cycle 4 Reload analysis. The August 4, 1994, submittal is the request to change the setpoint tolerances based on the November 1990 analysis. The reload analysis was approved by the staff in License Amendment No. 60, issued March 11, 1991 and the results of the analysis still remain applicable. Therefore the staff approves the proposed TS changes.
3.0 STATE CONSULTATION
In accordance with the Comission's regulations, the Connecticut State official was notified of the proposed issuance of the amendment. The State official had no coments.
4.0 ENVIRONMENTAL CONSIDERATION
Pursuant to 10 CFR 51.21, 51.32, and 51.35, an environmental assessment and finding of no significant impact have been prepared and published in the Federal Reaister on March 13, 1995 (60 FR 13476). Accordingly, based upon the environmental assessment, the staff has determined that the issuance of the amendment will not have a significant effect on the quality of the human environment.
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5.0 CONCLUSION
The Comission 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 Comission's regulations, and (3) the issuance of the amendment will not be inimical to the comon defense and security or to the health and safety of the public.
i Principal Contributor: S. Brewer Date:
March 17,1995 t
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i 7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION NORTHEAST NUCLEAR ENERGY COMPANY DOCKET NO. 50-423 NOTICE OF ISSUANCE OF AMENDMENT TO I
FACILITY OPERATING LICENSE i
i The U.S. Nuclear Regulatory Comission (Comission) has issued Amendment No.106 to Facility Operating License No. NPF-49 issued to Northeast Nuclear Energy Company (the licensee), which revised the Technical Specifications (TS) for operation of the Millstone Nuclear Power Station, Unit No. 3 located in New London County, Connecticut. The amendment is effective as of the date of 1ssur.nce.
i The amendment relaxes the setpoint tolerance for the pressurizer safety valves and the main steam safety valves from fl% to 13%.
The application for the amendment complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations. The Comission has made appropriate findings as required by the Act and the Comission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendment.
Notice of Consideration of Issuance of Amendment and Opportunity for Hearing in connection with this action was published in the FEDERAL REGISTER on October 12, 1994 (59 FR 51612). No request for a hearing or petition for leave to intervene was filed following this notice.
The Comission has prepared an Environmental Assessment related to the j
action and has determined not to prepare an environmental impact statement.
Based upon the environmental assessment, the Comission has concluded that the issuance of the amendment will not have a significant effect on the quality of the human environment (60 FR 13476).
F,
- For further details with respect to the action see (1) the application for amendment dated August 4,1994,(2) Amendment No. 106 to License No. NPF-49, (3) the Commission's related Safety Evaluation, and (4) the Commission's Environmental Assessment. All of these items are available for public inspection at the Commission's Public Document Room, the Gelman Building, 2120 L Street NW., Washington, DC, and at the local public document room located at i
the Learning Resource Center, Three Rivers Community-Technical College, Thames Valley Campus, 574 New London Turnpike, Norwich, CT 06360.
Dated at Rockville, Maryland, this 17th day of March 1995.
FOR THE CL REGULATORY COP 911SSION P
Vernon L. Rooney, Sr. Project Manager f
Project Directoratej!-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation i
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