L-02-058, Supplement to License Amendment Request Nos. 295 and 167 Re Creation of a Pressure and Temperature Limits Report for Each Unit, Per GL 96-03

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Supplement to License Amendment Request Nos. 295 and 167 Re Creation of a Pressure and Temperature Limits Report for Each Unit, Per GL 96-03
ML021570119
Person / Time
Site: Beaver Valley
Issue date: 05/31/2002
From: Pearson M
FirstEnergy Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
GL-96-003, L-02-058
Download: ML021570119 (8)
v • d • e


Text

FENOC Route Beaver Valley Power 168 Station PO. Box 4 FirstEnergyNuclear OperatingCompany Shippingport, PA 15077-0004 M. P. Pearson 724-682-7775 Fax: 724-682-1840 Director,Services & Projects May 31, 2002 L-02-058 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001

Subject:

Beaver Valley Power Station, Unit No. 1 and No. 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 Supplement to License Amendment Request Nos. 295 and 167 Pursuant to 10 CFR 50.90, FirstEnergy Nuclear Operating Company (FENOC) requested an amendment to the above licenses in the form of changes to the Technical Specifications. These changes were submitted by FENOC letter L-01-135, dated October 31, 2001. The License Amendment Requests propose the creation of a Pressure and Temperature Limits Report (PTLR) for each unit based on the guidance provided by Generic Letter 96-03 "Relocation of the Pressure Temperature Limit Curves and Low Temperature Overpressure Protection System Limits."

On April 17, 2002, a phone call was held with the NRC staff concerning their review of the subject License Amendment Requests (LARs). The NRC staff requested that the St. Lucie and Fort Calhoun data referenced in the supporting reports submitted with the LAR be added to the proposed PTLR for Beaver Valley Power Station Unit 1.

Attachment A contains the requested data as new tables for the Unit 1 PTLR as well as the other revised pages that reflect this change.

Attachment A also contains a revision to Table 4.2-3 of the proposed PTLR for Unit 1.

The revision adds a less than or equal sign (<) before the value specified in the table.

This editorial change provides consistency with Technical Specification 3.4.9.3, "Overpressure Protection Systems," for Unit 1. The revisions to the proposed PTLR are denoted by revision bars in the right margin.

The attached changes do not change the safety analysis or no significant hazard evaluation contained in L-0 1-135.

An implementation period of up to 60 days is requested following the effective date of this amendment.

Beaver Valley Power Station, Unit No. 1 and No. 2 Supplement to License Amendment Request Nos. 295 and 167 L-02-058 Page 2 If there are any questions concerning this matter, please contact Mr. Larry R. Freeland, Manager, Regulatory Affairs/Corrective Action at 724-682-5284.

I declare under penalty of perjury that the foregoing is true and correct. Executed on May 31, 2002.

Sincerely, M. P. Pearson c: Mr. D. S. Collins, Project Manager Mr. D. M. Kern, Sr. Resident Inspector Mr. H. J. Miller, NRC Region I Administrator Mr. D. A. Allard, Director BRP/DEP Mr. L. E. Ryan (BRP/DEP)

Attachment A to L-02-058 Affected Pages 4.2-iv 4.2-4 4.2-12 4.2-14 4.2-15

BVPS-1 LICENSING REQUIREMENTS MANUAL PRESSURE AND TEMPERATURE LIMITS REPORT List of Tables Table Title Page 4.2-1 Heatup Curve Data Points for 22 EFPY (TS 3.4.9.1) ............................................................ 4.2-9 4.2-2 Cooldown Curve Data Points for 22 EFPY (TS 3.4.9.1) ..................................................... 4.2-10 4.2-3 Overpressure Protection System (OPPS) Setpoints (TS 3.4.9.3) .................. 4.2-12 4.2-4 Calculation of Chemistry Factors Using Surveillance Capsule Data ............... 4.2-13 4.2-4a Calculation of Chemistry Factors (Based on St. Lucie and Fort Calhoun Surveillance Capsule Data) ................ 4.2-14 4.2-4b St. Lucie and Fort Calhoun Surveillance Weld Data ........................................................... 4.2-15 4.2-5 Reactor Vessel Beltline M aterial Properties ......................................................................... 4.2-16 4.2-6 Summary of Adjusted Reference Temperatures (ARTs) for 22 EFPY .............. 4.2-17 4.2-7 Calculation of Adjusted Reference Temperatures (ARTs) for 22 EFPY ............. 4.2-18 4.2-8 Reactor Vessel Toughness Data (Unirradiated) ................................................................... 4.2-19 4.2-9 RTPTS Calculation for Beltline Region Material at EOL (28 EFPY) ................ 4.2-20 4.2-10 RTPTS Calculation for Beltline Region Material at Life Extension (45 EFPY) .................... 4.2-21 Unit 1 PTLR 4.2-iv Revision 0 (Proposed Wording)

BVPS-1 LICENSING REQUIREMENTS MANUAL PRESSURE AND TEMPERATURE LIMITS REPORT 4.2.3 Supplemental Data Tables The following tables provide supplemental information on reactor vessel material properties and are provided to be consistent with Generic Letter 96-03. Some of the material property values shown were used as inputs to the P/T limits.

Table 4.2-4, taken from Reference 5, shows the calculation of the surveillance material chemistry factors using surveillance capsule data.

Table 4.2-4a, taken from Reference 2, shows the Calculation of Chemistry Factors based on St. Lucie and Fort Calhoun Surveillance Capsule Data.

Table 4.2-4b, taken from Reference 3, shows the St. Lucie and Fort Calhoun Surveillance Weld Data.

Table 4.2-5, taken from Reference 2, provides the reactor vessel beltline material property table.

Table 4.2-6, taken from Reference 2, provides a summary of the Adjusted Reference Temperature (ARTs) for 22 EFPY.

Table 4.2-7, taken from Reference 2, shows the calculation of ARTs for 22 EFPY.

Table 4.2-8 shows the Reactor Vessel Toughness Data (Unirradiated).

Table 4.2-9, taken from Reference 5, provides RTPTs values for 28 EFPY.

Table 4.2-10, taken from Reference 5, provides RTPTS values for 45 EFPY.

Unit 1 PTLR 4.2-4 Revision 0 (Proposed Wording)

BVPS-1 LICENSING REQUIREMENTS MANUAL PRESSURE AND TEMPERATURE LIMITS REPORT Table 4.2-3 Overpressure Protection System (OPPS) Setpoints (TS 3.4.9.3)

FUNCTION SETPOINT OPPS Enable Temperature 343 0 F PORV Setpoint *403 psig Sv Unit 1 PTLR 4.2-12 Revision 0 (Proposed Wording)

BVPS-1 LICENSING REQUIREMENTS MANUAL PRESSURE AND TEMPERATURE LIMITS REPORT Table 4.2-4a Calculation of Chemistry Factors(a)

(Based on St. Lucie and Fort Calhoun Surveillance Capsule Data)

Material Capsule Capsule fb) FF(c) ARTNDT(d) FF *ARTNDT FF' St. Lucie 970 0.627 0.869 72.3 76.1 0.755 Surveillance 1040 0.909 0.973 67.4 79.7 0.947 Weld Metal 2840 1.41 1.10 68.0 90.9 1.21 Heat 90136 SUM: 246.7 2.91 CF = Y(FF*RTNDT) + Z(FF 2) = (246.7) + (2.91) = 84.8 0F Fort Calhoun W-225 0.553 0.834 238 183.0 0.696 Surveillance W-265 0.771 0.927 221 194.1 0.859 Weld Metal W-275 1.28 1_1.07 219 226.2 1.14 Heat 305414 SUM: 603.3 2.695 CF = Y(FF*RTNDT) + (FF 2) = (603.3) + (2.695) = 223.9°F Notes:

(a) Use of St. Lucie and Fort Calhoun Surveillance Capsule Data approved by NRC letter dated February 20, 2002, "BEAVER VALLEY POWER STATION, UNIT 1 -ISSUANCE OF AMENDMENT RE: AMENDED PRESSURE-TEMPERATURE LIMITS (TAC NO.

MB2301)".

(b) f= Calculated fluence (x 1019 n/cm 2, E > 1.0 Mev) from Reference 2.

(c) FF = fluence factor = f(0. 2 8 -0.1

  • log f)

(d) ARTNDT values are the measured 30 ft-lb. shift values taken from Reference 2.

Unit 1 PTLR 4.2-14 Revision 0 (Proposed Wording)

BVPS-1 LICENSING REOUIREMENTS MANUAL PRESSURE AND TEMPERATURE LIMITS REPORT Table 4.2-4b St. Lucie and Fort Calhoun Surveillance Weld Data(a)(b)

Material Capsule Cu Ni Irradiated Fluence ARTNDT Temperature 'F 1019 n/cm 2 St. Lucie 970 0.2291 0.0699 546.7 0.627 72.3 Weld Metal 1040 0.2291 0.0699 546.7 0.909 67.4 Heat 90136 2840 0.2291 0.0699 546.7 1.41 68.0 Fort Calhoun W-225 0.35 0.60 527 0.553 238 Weld Metal W-265 0.35 0.60 534 0.771 221 Heat 305414 W-275 0.35 0.60 538 1.28 219 Notes:

(a) Use of St. Lucie and Fort Calhoun Surveillance Capsule Data approved by NRC letter dated February 20, 2002, "BEAVER VALLEY POWER STATION, UNIT 1 -ISSUANCE OF AMENDMENT RE: AMENDED PRESSURE-TEMPERATURE LIMITS (TAC NO.

MB2301)".

(b) Data contained in this table was obtained from Reference 3.

Unit 1 PTLR 4.2-15 Revision 0 (Proposed Wording)

Text

FENOC Route Beaver Valley Power 168 Station PO. Box 4 FirstEnergyNuclear OperatingCompany Shippingport, PA 15077-0004 M. P. Pearson 724-682-7775 Fax: 724-682-1840 Director,Services & Projects May 31, 2002 L-02-058 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001

Subject:

Beaver Valley Power Station, Unit No. 1 and No. 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 Supplement to License Amendment Request Nos. 295 and 167 Pursuant to 10 CFR 50.90, FirstEnergy Nuclear Operating Company (FENOC) requested an amendment to the above licenses in the form of changes to the Technical Specifications. These changes were submitted by FENOC letter L-01-135, dated October 31, 2001. The License Amendment Requests propose the creation of a Pressure and Temperature Limits Report (PTLR) for each unit based on the guidance provided by Generic Letter 96-03 "Relocation of the Pressure Temperature Limit Curves and Low Temperature Overpressure Protection System Limits."

On April 17, 2002, a phone call was held with the NRC staff concerning their review of the subject License Amendment Requests (LARs). The NRC staff requested that the St. Lucie and Fort Calhoun data referenced in the supporting reports submitted with the LAR be added to the proposed PTLR for Beaver Valley Power Station Unit 1.

Attachment A contains the requested data as new tables for the Unit 1 PTLR as well as the other revised pages that reflect this change.

Attachment A also contains a revision to Table 4.2-3 of the proposed PTLR for Unit 1.

The revision adds a less than or equal sign (<) before the value specified in the table.

This editorial change provides consistency with Technical Specification 3.4.9.3, "Overpressure Protection Systems," for Unit 1. The revisions to the proposed PTLR are denoted by revision bars in the right margin.

The attached changes do not change the safety analysis or no significant hazard evaluation contained in L-0 1-135.

An implementation period of up to 60 days is requested following the effective date of this amendment.

Beaver Valley Power Station, Unit No. 1 and No. 2 Supplement to License Amendment Request Nos. 295 and 167 L-02-058 Page 2 If there are any questions concerning this matter, please contact Mr. Larry R. Freeland, Manager, Regulatory Affairs/Corrective Action at 724-682-5284.

I declare under penalty of perjury that the foregoing is true and correct. Executed on May 31, 2002.

Sincerely, M. P. Pearson c: Mr. D. S. Collins, Project Manager Mr. D. M. Kern, Sr. Resident Inspector Mr. H. J. Miller, NRC Region I Administrator Mr. D. A. Allard, Director BRP/DEP Mr. L. E. Ryan (BRP/DEP)

Attachment A to L-02-058 Affected Pages 4.2-iv 4.2-4 4.2-12 4.2-14 4.2-15

BVPS-1 LICENSING REQUIREMENTS MANUAL PRESSURE AND TEMPERATURE LIMITS REPORT List of Tables Table Title Page 4.2-1 Heatup Curve Data Points for 22 EFPY (TS 3.4.9.1) ............................................................ 4.2-9 4.2-2 Cooldown Curve Data Points for 22 EFPY (TS 3.4.9.1) ..................................................... 4.2-10 4.2-3 Overpressure Protection System (OPPS) Setpoints (TS 3.4.9.3) .................. 4.2-12 4.2-4 Calculation of Chemistry Factors Using Surveillance Capsule Data ............... 4.2-13 4.2-4a Calculation of Chemistry Factors (Based on St. Lucie and Fort Calhoun Surveillance Capsule Data) ................ 4.2-14 4.2-4b St. Lucie and Fort Calhoun Surveillance Weld Data ........................................................... 4.2-15 4.2-5 Reactor Vessel Beltline M aterial Properties ......................................................................... 4.2-16 4.2-6 Summary of Adjusted Reference Temperatures (ARTs) for 22 EFPY .............. 4.2-17 4.2-7 Calculation of Adjusted Reference Temperatures (ARTs) for 22 EFPY ............. 4.2-18 4.2-8 Reactor Vessel Toughness Data (Unirradiated) ................................................................... 4.2-19 4.2-9 RTPTS Calculation for Beltline Region Material at EOL (28 EFPY) ................ 4.2-20 4.2-10 RTPTS Calculation for Beltline Region Material at Life Extension (45 EFPY) .................... 4.2-21 Unit 1 PTLR 4.2-iv Revision 0 (Proposed Wording)

BVPS-1 LICENSING REQUIREMENTS MANUAL PRESSURE AND TEMPERATURE LIMITS REPORT 4.2.3 Supplemental Data Tables The following tables provide supplemental information on reactor vessel material properties and are provided to be consistent with Generic Letter 96-03. Some of the material property values shown were used as inputs to the P/T limits.

Table 4.2-4, taken from Reference 5, shows the calculation of the surveillance material chemistry factors using surveillance capsule data.

Table 4.2-4a, taken from Reference 2, shows the Calculation of Chemistry Factors based on St. Lucie and Fort Calhoun Surveillance Capsule Data.

Table 4.2-4b, taken from Reference 3, shows the St. Lucie and Fort Calhoun Surveillance Weld Data.

Table 4.2-5, taken from Reference 2, provides the reactor vessel beltline material property table.

Table 4.2-6, taken from Reference 2, provides a summary of the Adjusted Reference Temperature (ARTs) for 22 EFPY.

Table 4.2-7, taken from Reference 2, shows the calculation of ARTs for 22 EFPY.

Table 4.2-8 shows the Reactor Vessel Toughness Data (Unirradiated).

Table 4.2-9, taken from Reference 5, provides RTPTs values for 28 EFPY.

Table 4.2-10, taken from Reference 5, provides RTPTS values for 45 EFPY.

Unit 1 PTLR 4.2-4 Revision 0 (Proposed Wording)

BVPS-1 LICENSING REQUIREMENTS MANUAL PRESSURE AND TEMPERATURE LIMITS REPORT Table 4.2-3 Overpressure Protection System (OPPS) Setpoints (TS 3.4.9.3)

FUNCTION SETPOINT OPPS Enable Temperature 343 0 F PORV Setpoint *403 psig Sv Unit 1 PTLR 4.2-12 Revision 0 (Proposed Wording)

BVPS-1 LICENSING REQUIREMENTS MANUAL PRESSURE AND TEMPERATURE LIMITS REPORT Table 4.2-4a Calculation of Chemistry Factors(a)

(Based on St. Lucie and Fort Calhoun Surveillance Capsule Data)

Material Capsule Capsule fb) FF(c) ARTNDT(d) FF *ARTNDT FF' St. Lucie 970 0.627 0.869 72.3 76.1 0.755 Surveillance 1040 0.909 0.973 67.4 79.7 0.947 Weld Metal 2840 1.41 1.10 68.0 90.9 1.21 Heat 90136 SUM: 246.7 2.91 CF = Y(FF*RTNDT) + Z(FF 2) = (246.7) + (2.91) = 84.8 0F Fort Calhoun W-225 0.553 0.834 238 183.0 0.696 Surveillance W-265 0.771 0.927 221 194.1 0.859 Weld Metal W-275 1.28 1_1.07 219 226.2 1.14 Heat 305414 SUM: 603.3 2.695 CF = Y(FF*RTNDT) + (FF 2) = (603.3) + (2.695) = 223.9°F Notes:

(a) Use of St. Lucie and Fort Calhoun Surveillance Capsule Data approved by NRC letter dated February 20, 2002, "BEAVER VALLEY POWER STATION, UNIT 1 -ISSUANCE OF AMENDMENT RE: AMENDED PRESSURE-TEMPERATURE LIMITS (TAC NO.

MB2301)".

(b) f= Calculated fluence (x 1019 n/cm 2, E > 1.0 Mev) from Reference 2.

(c) FF = fluence factor = f(0. 2 8 -0.1

  • log f)

(d) ARTNDT values are the measured 30 ft-lb. shift values taken from Reference 2.

Unit 1 PTLR 4.2-14 Revision 0 (Proposed Wording)

BVPS-1 LICENSING REOUIREMENTS MANUAL PRESSURE AND TEMPERATURE LIMITS REPORT Table 4.2-4b St. Lucie and Fort Calhoun Surveillance Weld Data(a)(b)

Material Capsule Cu Ni Irradiated Fluence ARTNDT Temperature 'F 1019 n/cm 2 St. Lucie 970 0.2291 0.0699 546.7 0.627 72.3 Weld Metal 1040 0.2291 0.0699 546.7 0.909 67.4 Heat 90136 2840 0.2291 0.0699 546.7 1.41 68.0 Fort Calhoun W-225 0.35 0.60 527 0.553 238 Weld Metal W-265 0.35 0.60 534 0.771 221 Heat 305414 W-275 0.35 0.60 538 1.28 219 Notes:

(a) Use of St. Lucie and Fort Calhoun Surveillance Capsule Data approved by NRC letter dated February 20, 2002, "BEAVER VALLEY POWER STATION, UNIT 1 -ISSUANCE OF AMENDMENT RE: AMENDED PRESSURE-TEMPERATURE LIMITS (TAC NO.

MB2301)".

(b) Data contained in this table was obtained from Reference 3.

Unit 1 PTLR 4.2-15 Revision 0 (Proposed Wording)

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