L-08-126, Pressure and Temperature Limits Report, Revision 2-1
| ML080940475 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 03/31/2008 |
| From: | Sena P FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-08-126 | |
| Download: ML080940475 (5) | |
Text
FENOC FirstEnergy Nuclear Operating Company Peter P. Sena III 724-682-5234 Site Vice President Fax: 724-643-8069 March 31, 2008 L-08-126 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Unit 2 Pressure and Temperature Limits Report, Revision 2-1 FirstEnergy Nuclear Operating Company (FENOC) hereby submits a revised page of the Pressure and Temperature Limits Report (PTLR) for Beaver Valley Power Station (BVPS) Unit No. 2 as required by Section 5.6.4.c of the BVPS Technical Specifications.
BVPS Unit No. 2 PTLR Revision 2-1, page 5.2-3, is enclosed.
This revision of the BVPS Unit No. 2 PTLR, effective March 20, 2008, was made to correct the description of switches (one in each train) used to activate the over pressure protection system, by deleting the word "keylock." The error was inadvertently introduced when the PTLR was created, and nearly identical paragraphs, that reference keylock switches, were added to both the BVPS Unit No. 1 and Unit No. 2 PTLRs. The error was subsequently identified and corrected in accordance with plant procedures.
There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Manager -
FENOC Fleet Licensing, at 330-761-6071.
SincI Peter P. Sena III odJ
FENOC FirstEnergy Nuclear Operating Company Peter P. Sena II1 724-682-5234 Site Vice President Fax: 724-643-8069 March 31, 2008 L-08-126 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Unit 2 Pressure and Temperature Limits Report, Revision 2-1 FirstEnergy Nuclear Operating Company (FENOC) hereby submits a revised page of the Pressure and Temperature Limits Report (PTLR) for Beaver Valley Power Station (BVPS) Unit No. 2 as required by Section 5.6.4.c of the BVPS Technical Specifications.
BVPS Unit No. 2 PTLR Revision 2-1, page 5.2-3, is enclosed.
This revision of the BVPS Unit No. 2 PTLR, effective March 20, 2008, was made to correct the description of switches (one in each train) used to activate the over pressure protection system, by deleting the word "keylock." The error was inadvertently introduced when the PTLR was created, and nearly identical paragraphs, that reference keylock switches, were added to both the BVPS Unit No. 1 and Unit No. 2 PTLRs. The error was subsequently identified and corrected in accordance with plant procedures.
There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Manager -
FENOC Fleet Licensing, at 330-761-6071.
Peter P. Sena III 00/
Beaver Valley Power Station, Unit No. 2 L-08-126 Page 2
Enclosure:
Beaver Valley Power Station Unit No. 2, Pressure and Temperature Limits Report, Revision 2-1, Page 5.2-3 cc:
Mr. S. J. Collins, NRC Region I Administrator Mr. D. L. Werkheiser, NRC Senior Resident Inspector Ms. N. S. Morgan, NRR Project Manager Mr. D. J. Allard, Director BRP/DEP Mr. L. E. Ryan (BRP/DEP)
L-08-126 Enclosure Beaver Valley Power Station Unit No. 2 Pressure and Temperature Limits Report Revision 2-1, Page 5.2-3
,Licensing Requirements Manual Pressure and Temperature Limits Report 5.2 5.2 Pressure and Temperature Limits Report 5.2.1.3 OPPS Enable Temperature (LCO 3.4.12)
Two different temperatures are used to determine the OPPS enable temperature, they are the arming temperature and the calculated enable temperature. The arming temperature (when the OPPS rendered operable) is established per ASME Section XI, Appendix G. At this temperature, a steam bubble would be present in the pressurizer, thus reducing the potential of a water hammer discharge that could challenge the piping limits. Based on this method, the arming temperature with uncertainty is 237°F.
The calculated enable temperature is based on either a RCS temperature of less than 200°F or materials concerns (reactor vessel metal temperature less than RTNDT + 50 0F), whichever is greater. The calculated enable temperature does not address the piping limit attributed to a water hammer discharge. The calculated enable temperature is 2400F.
As the calculated enable temperature is higher and, therefore, more conservative than the arming temperature, the OPPS enable temperature, as shown in Table 5.2-3, is set to equal the calculated enable temperature.
The calculation method governing the heatup and cooldown of the RCS requires the arming of the OPPS at and below the OPPS enable temperature specified in Table 5.2-3, and disarming of the OPPS above this temperature. The OPPS is required to be enabled, i.e., OPERABLE, when any RCS cold leg temperature is less than or equal to this temperature.
From a plant operations viewpoint the terms "armed" and "enabled" are synonymous when it comes to activating the OPPS. As stated in the applicable operating procedure, the OPPS is activated (armed/enabled) manually before entering the applicability of LCO 3.4.12. This is accomplished by placing two switches (one in each train) into their "ARM" position. Once OPPS is activated (armed/enabled) reactor coolant system pressure transmitters will signal a rise in system pressure above the variable OPPS setpoint. This will initiate an alarm in the control room and open the OPPS PORVs.
5.2.1.4 Reactor Vessel Boltup Temperature (LCO 3.4.3)
The minimum boltup temperature for the Reactor Vessel Flange shall be >_ 60°F.
Boltup is a condition in which the reactor vessel head is installed with tension applied to any stud, and with the RCS vented to atmosphere.
PTLR Revision 2-1 Beaver Valley Unit 2 5.2 - 3 LRM Revision 55