ML20083M140
| ML20083M140 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 05/11/1995 |
| From: | Saccomando D COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9505190122 | |
| Download: ML20083M140 (2) | |
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ji Downers Grove,11,(dH15 May'll, 1995 Office of Nuclear Regulation U.S. Nuclear Regulatory Commission-Washington, D.C. 20555 Attn:
Document Control Desk a
Subject:
Clarification of Information Regarding Braidwood Stations Request to Use American Society of Mechanical Engineers Code Case N-514 in the Determination of Low Temperature Overpressure Protection System Setpoint Braidwood Station Units 1 and 2 NRC Docket Numbers 50-456/457
References:
1.
D.
Saccomando letter to NRC dated November 30, 1994, Transmitting Request to Use ASME Code Case N-514 2.
D.
Saccomando letter to NRC dated December 16, 1995, transmitting Technical Specification Amendment Request for Nominal PORV Pressure Relief Setpoint Versus RCS Temperature for the Cold Overpressure Protection System 3.
Teleconference dated May 2 between Commonwealth Edison Company and the Nuclear Regulatory Commission Regarding the December 16, 1995, Technical Specification Submittal During the Reference Teleconference it was noted that Commonwealth Edison Company (Comed) needed to clarify that it is requesting an exemption request per 10CFR50.12 to use American Society of Mechanical Engineers (ASME)Section XI Code Case N-514, " Low Temperature Overpressure Protection Section XI, Division 1,"
in the determination of Low Temperature Overpressure Protection System (LTOPS) Setpoints for Braidwood Nuclear Station Units 1 and 2.
10CFR50.12 (a) (2 ) (iii) allows for the Commission to consider granting an exemption under special circumstances; specifically, if compliance would result in undue hardship.
As stated in Reference letter 1,
" Compliance with the current requirements for determination of LTOPS setpoints included in 10CFR50 Appendix G results in hardships for Braidwood Station without a concurrent increase in the level of quality and safety.
Application of the current LTOPS setpoint determination method reduces operating flexibility by reducing the margin between the maximum allowed Reactor Coolant System (RCS) pressure and Kinla\\twd\\n514 9505190122 950511
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NRC Document Control Desk. May 11, 1995 the minimum RCS pressure forLReactor Coolant Pump (RCP) i
. - yf operation with no. concurrent increase-in protection against non-ductile failure of the Reactor Pressure Vessel.
The current methodology also increases the likelihood of.LTOPS actuation at lower setpoints,-and reduces'the amount'of separation of the setpoints for'the Power' Operated Relief Valves (PORV) used in the LTOPS system.
This endangers the RCP seals as actuation of LTOPS at setpoints determined by the current methodology may cause.RCS pressure to drop below the minimum needed to maintain proper RCP seal differential pressure."
Approval of this request to'use Code Case N-514 in the determination of LTOPS setpoints is necessary'to allow Braidwood Station-to obtain approval of new LTOPS Technical Specification curves which was submitted in Reference 2.
f If you have any questions regarding this correspondence, please
-contact this office.
Sincerely, s
A#
O Denise M. Sbcomando Nuclear Licensing Administrator r
cc:
R. Assa, Braidwood Project Manager-NRR S. Dupont, Senior Resident Inspector-Braidwood i
J. Martin,-Regional Administrator-RIII Office of Nuclear Safety-IDNS Kinta\\bwd\\n514 I
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