Text

Issuance of Amendment Regarding the 8-Percent Extended Power Uprate, Technical Specifications
	ML062020066
Person / Time
Site:	Beaver Valley
Issue date:	07/19/2006
From:	Colburn T; NRC/NRR/ADRO/DORL/LPLI-1
To:	Lash J; FirstEnergy Nuclear Operating Co
References
	TAC MC4645, TAC MC4646
	Download: ML062020066 (12)
	v • d • e

(3) FENOC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) FENOC, pursuant to the Act and 1.0 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; (5) FENOC, pursuant to the Act and 10 CER Parts 30, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. This amended license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter 1: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level FENOC is authorized to operate the facility at a steady state reactor core power level of 2900 megawatts thermal.

(2) Technical Specifications The Technical Speacifications contained in Appendix A, as revised through Amendment No. 275 ,are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

(3) Auxiliary River Water System (Deleted by Amendment No. 8).

Amendment No. 275

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 ACCUMULATORS.................................. 3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - Tavg Ž! 350OF................ 3/4 5-3 3/4.5.3 ECCS SUBSYSTEMS - Tavg < 350-F............... 3/4 5-6 3/4.5.4 HHSI FLOW PATH................................ 3/4 5-7 I

3/4.5.5 SEAL INJECTION FLOW.......................... 3/4 5-8 3/4.6 CONTAINMENT SYSTEMS 314..6.1 PRIMARY CONTAINMENT 3/4.6.1.1 Containment Integrity.................... 3/4 6-1 3/4.6.1.2 Containment Leakage --.................. 3/4 6-2 3/4.6.1.3 Containment Air Locks.................... 3/4 6-5 3/4.6.1.4 Internal Pressure......................... 3/4 6-6 3/4.6.1.5 Air Temperature........................... 3/4 6-8 3/4.6.1.6 Containment Structural Integrity......... 3/4 6-10 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4.6.2.1 Containment Quench Spray System.......... 3/4 6-11 3/4.6.2.2 Containment Recirculation Spray System 3/4 6-13 3/4.6.2.3 Chemical Addition System ................. 3/4 6-15 3/4.6.3 CONTAINMENT ISOLATION VALVES............. 3/4 6-17 BEAVER VALLEY - UNIT 1IiAeden V1 o 275 Amendment No. 7

.1.0 DEFINITIONS DEFINED TERMS 1.1 The DEFINED TERMS of this section appear in capitalized type and are applicable throughout these Technical Specifications.

THERMAL POWER 1.2 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

RATED THERMAL POWER 1.3 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant as specified in the Licensing Requirements Manual, and shall not exceed 2900 MWt.

OPERATIONAL MODE 1.4 An OPERATIONAL MODE shall correspond to any one inclusive combination of core reactivity condition, power level and average reactor coolant temperature specified in Table 1.1.

ACTION 1.5 ACTION shall be those additional requirements specified as corollary statements to each principle specification and shall be part of the specifications.

OPERABLE - OPERABILITY 1.6 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s). Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electric power sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function(s) are also capable of performing their related safety function(s).

BEAVER VALLEY - UNIT 1 11Annmn 1-1 o 275 Amendment No. 7

REACTIVITY CONTROL SYSTEMS REFUELING WATER STORAGE TANK (RWST)-

LIMITING CONDITION FOR OPERATION 3.1.2.8 The RWST shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3' & 4.

ACTION:

With the refueling water storage tank inoperable, restore the tank to OPERABLE status within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.1.2.8 The RWST shall be verified OPERABLE:

a. At least once per 7 days by:

1. Verifying the boron concentration is between 2,400 and 2,600 ppm, and

2. Verifying a contained volume between 439,050 gallons and 441,100 gallons of borated water.

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the RWST solution temperature is Žý 45'F and *ý 65'F when the RWST ambient air temperature is < 45 0F or > 650F. I BEAVER VALLEY - UNIT 1 .3/4 1-16 Amendment No . 275 (Next page is 3/4 1-17a)

TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATIOM MINIMUM TOTAL NO. CHANNELS CHANNELS ALLOWABLE APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE VALUE MODES ACTION

1. Manual Reactor Trip 2 1 2 Not Applicable 1, 2, 3(3), 12 4(3) and 5(3)

2. Power Range, Neutron Flux

a. High Setpoint 4 2 3 1, 2

-<109.5% of RATED 2 THERMAL POWER

b. Low Setpoint 4 2 3 <-25.5% OF RATED ~() 2 2 THER1MAL POWER

3. Power Range, Neutron Flux 4 2 3 1, 2 High Positive Rate < 5.5% of RATED 2 THERMAL POWER with a time constant

Ž:2 seconds

4. DELETED

5. Intermediate Range, Neutron 2 1 2 1(1), 23(3), 3 Flux <-27.9% of RATED THERMAL POWER and 5 (3) 4 (3)

6. Source Range, Neutron Flux

a. With Rod Withdrawal 2 1 2 <-1.3 x 105 counts 2(2), 3(3) 4 Capability per second 4 (3) and 5 (3)

b. With All Rods Fully 2 0 1 Not Applicable 3(8) 4(8) 5 Inserted and Without Rod Withdrawal Capability and 5(8)

BEAVER VALLEY - UNIT 13/3-AenetNo27 3/4 3-2 Amendment No. 275

TABLE 3.3-1 (Continued)

ACTION 7 - With the number of OPERABLE channels ()one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels per Specification 4.3.1.1.1.

ACTION 8 - With the number of OPERABLE channels one less than the Total Number of. Channels and with the THERMAL POWER level above P-9, place the inoperable channel in the I tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; operation may continue until performance of the next required CHANNEL FUNCTIONAL TEST.

ACTION 9 - Not applicable.

ACTION 10 - Not applicable.

ACTION 11 - With less than the Minimum Number of Channels OPERABLE, operation may continue provided the inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 12 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, re*store the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and/or open the reactor trip breakers.

ACTION 39 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the reactor trip breakers within the next hour.

(6) An OPERABLE hot leg -channel consists of: 1) three RTDs per hot leg, or 2) two RTDs per hot leg with the failed RTD disconnected and the required bias applied.

BEAVER VALLEY - UNIT 13/3-AmnetNo27 3/4 3-7 Amendment No. 275

TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS Channel Modes in Which Channel Channel Functional Surveillance Functiona-l Unit Check Calibration Test Required

1. Manual Reactor Trip N. A. N. A. S/U (1) .N.A.

2. Power Range, Neutron Flux

a. High Setpoint S Q 1,2 and Q (6)

b. Low Setpoint S 2

3. Power Range, Neutron Flux, N. A. 6 Q 1,.2 R()

High Positive Rate

4. DELETED I 6

5. Intermediate Range, S R( ) 1 2, 3 (14)

Neutron Flux

6. Source Range ,Neutron Flux 6

a. With Rod Withdrawal S R( ) Q(8) 2, 3 (14) 4 (14)

Capability and 5 (141 6

b. With All Rods Fully S R () Q (8) 3, 4 and 5 Inserted and Without Rod Withdrawal Capability

7. Overtemperature AT S R (6 ) Q 1, 2

8. Overpower AT S R Q 1, 2

9. Pressurizer Pressure-Low S R Q 1, 2

10. Pressurizer Pressure-High S R Q 1, 2 11.' Pressurizer Water S R Q 1, 2 Level -High BEAVER VALLEY - UNIT 13/3-1AiedntN27 3/4 3-11 Amendment No. 275

TABLE 3.3-3 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS ALLOWABLE APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE VALUE MODES ACTION

1. SAFETY INJECTION AND FEEDWATER ISOLATION

a. Manual Initiation 2 2 Not Applicable 1, 2, 3, 4 18

b. Automatic Actuation 2 2 Not Applicable 1, 2, 3, 4 13, 36 Logic

c. Containment 3 2 2 :55.33 psig 1, 2, 3 14 Pressure-High

d. Pressurizer Pressure-Low 3 2 2 Žt1841 psig 1, 2, 14 3(1)

e. Steamline Pressure-Low 3/loop 2/loop 2/loop Žt495.8 psig steam 1, 2, 14 any loop any loop line pressure* 3(1)

I

Time constants utilized in the lead-lag controllers for Steam Line Pressure-Low are Tri> 50 seconds and Tr2 5 seconds. CHANNEL CALIBRATION shall ensure that these time constants are adjusted to these values.

BEAVER VALLEY - UNIT 1 3/4 3431 3-15 Amendment ninmn No.o 275 7

TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTBUMENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS ALLOWABLE APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE -VALUE MODES ACTION

4. STEAM LINE ISOLATION

a. Manual 2/steam 1/steam 2/operat- Not Applicable 1, 2, 3 1.8 line line ing steam line

b. Automatic Actuation 2 1 2 Not Applicable 1, 2, 3 13 Logic

c. Containment Pressure 3 2 2 1, 2, 3

< 7.33 psig 14 Intermediate-High-High

d. Steamline Pressure-Low 3/loop 2/loop 2/loop Ž 495.8 psig steam 1, 2, 14 any loop any loop line pressure* 3 (1) I

e. Steamline Pressure Rate- 3/ loop 2/loop 2/operat- *104.2, psi with 3(2) 14 High Negative any loop ing loop a time constant

-1 50 seconds

5. TURBINE TRIP & FEEDWATER ISOLATION

a. Steam Generator Water 3/loop 2 /loop 2 /loop, :590.2% of narrow 1, 2, 3 14 Level--High-High, P-14 in any in each range instrument operating operating span each steam loop loop generator

Time constants utilized in the lead-lag controllers for Steam Line Pressure-Low are x1 > 50 seconds and T2 :S 5 seconds. CHANNEL CALIBRATION shall ensure that these time constants are adjusted to these values.

BEAVER VALLEY - UNIT 13/3-8medntN.2. 3/4 3-18 Amendment No. 275'.

REACTOR COOLANT SYSTEM 3/4.4.3 SAFETY VAILVES LIMITING CONDITION FOR OPERATION 3.4.3 All pressurizer code safety valves shall be OPERABLE with a lift setting* of 2485 PSIG +/-3%.**

APPLICABILITY: MODES 1, 2 and 3, MODE 4 with all RCS cold leg temperatures > the enable temperature specified in the PTLR.

ACTION:

a. with one pressurizer code safety valve inoperable, either restore the inoperable valve to OPERABLE status within 15 minutes or be in HOT SHUTDOWN with any RCS cold leg temperature *5 the enable temperature specified in the PTLR and apply RCS overpressure protection requirements in accordance with Specification 3.4.9.3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b. With a pressurizer code safety valve having discharged liquid water from a water solid pressurizer to mitigate an overpressure event, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in HOT SHUTDOWN with any RCS cold leg temperature *: the enable temperature specified in the PTLR and apply 'RCS 'overpressure protection requirements in accordance with Specification 3.4.9.3 within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEI LLANCE REQUIREMENTS 4.4.3 No additional requirements other than those required by Specification 4 .0.5.

The Lift Setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.

- Within +/- 1% following pressurizer code safety valve testing.

BEAVER VALLEY - UNIT I3/4-AmdenNo27 3/4 4-6 Amendment No. 275

REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.8 The specific activity of the primary coolant shall be limited to:

a. *0.35 tiCi/gram DOSE EQUIVALENT 1-131, and

b. 5 100lE pCi/grain.

APPLICABILITY: MODES 1, 2, 3, 4 and 5.

ACTION:

MODES 1, 2, and 3*

a. with the specific activity of the primary coolant > 0.35 pCi/gram DOSE EQUIVALENT 1-131(1) for more than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time interval or exceeding the limit line shown on Figure 3.4-1, be in HOT STANDBY with' Tavg

< 500'F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. with the. specific activity of the primary coolant > 100lE pCi/gram, be in* HOT STANDBY with Tavg <-5000 F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

MODES 1, 2, 3, 4 and 5

a. With the specific activity of the primary coolant > 0.35 pCi/gram DOSE EQUIVALENT 1-131 or > 100/E pCi/gram, perform the sampling and analysis requirement of item 4a of Table 4.4-12 until the specific activity of the primary coolant is restored to within its limits.

SURVEILLANCE REQUIREMENTS 4.4.8 The specific activity of the primary coolant shall be determined to be within the limits by performance of the sampling and analysis program of Table 4.4-12.

With Tavg Ž: 500OF (1) Specification 3.0.4.c is applicable.

BEAV ER VALLEY -UNIT 1 3/4 4-18 Amendment No. 275 (next page is 3/4 4-20)

TABLE 4.4-12 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM TYPE OF MEASUREMENT MINIMUM MODES IN WHICH AND ANALYSIS FREQUENCY SURVEILLANCE REQUIRED_

1. Gross Activity Determination 3 times per 7 days with a 1, 2, 3, 4 maximum time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months between samples.

2. Isotopic Analysis for DOSE EQUIVA- 1 per 14 days 1, LENT 1-131 Concentration

3. Radiochemical for EDetermination 1 per 6 months 1,

4. Isotopic Analysis for Iodine a) Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , 1#, 2#, 3#,. 4#, 5#

Including 1-131, 1-133, and 1-135 whenever the specific activity exceeds 0.35 jiCi/gram DOSE I.

EQUIVALENT I-131 or 100/E giCi/gram, and b) One sample between 1, 2, 3 2 & 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months following a THERMAL POWER change exceeding 15 percent of the RATED THERMAL POWER within a one hour period.

Until the specific activity of the primary coolant system is restored within its limits.

BEAVER VALLEY - UNIT 1 3442 3/4 4-20 Amendment mnmn o 275 No. 7

250 C-) 200 U-a.

UNACCEPTABLE OPERATION C.)

0 150 100 CY 0U 0 ACCEPTAL OPRTON 50 co 0

20 30 40 150 60 70 80 90 lt PERCENT OF RATED THERMAL POWER FIGURE 3.4-1 DOSE EQUIVALENT 1-131 Primary Coolant Specific Activity Limit Versus Percent of RATED THERMAL POWER with the Primary Coolant Specific Activity > 0.35 pCi/gram DOSE EQUIVALENT 1-131 I BEAVER VALLEY - UNIT 1I/ 3/4 4-21

-1Aenmn Amendment No. o 2T) 7

EMERGENCY CORE COOLING SYSTEMS 3/4.5.2 EGGS SUBSYSTEMS - Tavg Ž! 350OF LIMITING CONDITION FOR OPERATION 3.5.2 T1w?) separate. and independent EGGS subsystems shall be OPERABLE~1 ~ with each subsystem comprised of:

a. One OPERABLE centrifugal charging pump,

b. One OPERABLE low head safety injection pump, and C. An OPERABLE flow path capable of taking suction from the refueling water storage tank on a safety injection signal and transferring suction to the containment sumnp during the recirculation phase of operation.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a. With one EGGS subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b. In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted in accordance with 10 CFR 50.4 within 30 days describing the circumstances of the actuation and the total accumulated actuation cycles to date.

(1) In MODE 3, one of the required centrifugal charging pumps may be made incapable of injecting to support transition into or from the Applicability of Specification 3.4.9.3 for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or until the temperature of all RCS cold legs exceeds the OPPS enable temperature specified in the PTLR plus 250F, whichever comes first.

(2) In MODE 3, the ECCS automatic HESI flow path may be isolated to support transition into or from the Applicability of Specification 3.5.4 for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or until the temperature of all RCS cold legs exceeds the OPPS enable temperature specified in the PTLR plus 250F, whichever comes first.

BEAVER VALLEY - UNIT I / 5-3 3/4 - mnmn No.

Amendment o 7 275

EMERGENCY CORE COOLING SYSTEMS 3/4.5.3 ECCS SUBSYSTEMS -. Tvg < 350OF LIMITING CONDITION FOR OPERATION 3.5.3 As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE:

a. One OPERABLE centrifugal charging pump,

b. One OPERABLE Low Head Safety Injection Pump, and C. An OPERABLE flow path capable of taking suction from the refueling water storage tank upon being manually realigned and transferring suction to the containment sumnp during the recirculation phase of operation.

APPLICABILITY: MODE 4.

ACTION:

--- -- -- ------------------ GENERAL NOTE -------------

Specification 3.0.4.b is not applicable to ECCS centrifugal charging pumps.

a. With no ECCS subsystem OPERABLE because of the inoperability of either the centrifugal charging pump or the flow path from the refueling water storage tank, restore at least one ECCS subsystem to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months .

b. In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted in accordance with 10 CFR 50.4 within 30 days describing the circumstances of the actuation and the total accumulated actuation cycles to date.

SURVEILLANCE REQUIREMENTS 4.5.3.1 The ECCS subsystem shall be demonstrated OPERABLE by the performance of each of the Surveillance Requirements of 4.5.2 except for requirements 4.5.2.c, 4.5.2.f.2 and 4.5.2.f.3.

BEAVER VALLEY - UNIT 1 3456.iednn 3/4 5-6 o Amendment No. 7 275

EMERGENCY CORE COOLING SYSTEMS 3/4.5.4 HHSI FLOW PATH LIMITING CONDITION FOR OPERATION 3.5.4 The ECCS automatic high head safety injection (HHSI) flow path shall be isolated.

APPLICABILITY: MODE 4 when any RCS cold leg temperature is less than or equal to the enable temperature specified in the PTLR, MODE 5, MODE 6 when the reactor vessel head is on.

ACTION:

With the ECCS automatic HHSI flow path not isolated, isolate the flow path within I hour.

SURVEILLANCE REQUIREMENTS 4.5.4. The ECCS automatic HHSI flow path shall be verified isolated at least once per 7 days except for purposes of flow testing or valve stroke testing.

BEAVER VALLEY - UNIT 13/5-AmnetNo27 3/4 5-7 Amendment No. 2T:)

3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE MAIN STEAM SAFE-TY VALVES (MSSVS)

LIMITING CONDITION FOR OPERATION 3.7.1.1 Five IASSVs per steam generator shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

-- - -- -- ------------- GENERAL NOTE----------------------------------

Separate ACTION entry is allowed for each MSSV.

a. With one or more steam generators with one MSSV inoperable and the Moderator Temperature Coefficient (MTC) zero or negative at all power levels, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months reduce THERMAL POWER to less than or equal to 57% RTP; otherwise, be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. With one or more steam generators with two or more MSSVs inoperable, or with one or more steam generators with one MSSV inoperable and the MTC positive at any power level, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months reduce THERMAL POWER to less than or equal to the Maximum Allowable % RTP specified in Table 3.7-1 for the number of OPERABLE MSSVs, and reduce the Power Range Neutron Flux-High reactor trip setpoint to less than or equal to the Maximum Allowable % RTP specified in Table 3.7-1 for the number of OPERABLE MSSVs within the next 32 hours3.703704e-4 days 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months (1); otherwise, be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

C. With one or more steam generators with four or more IASSVs inoperable, within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months be in HOT STANDBY and in HOT SHU~TDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.7.1.1 Verify ()each required MSSV lift setpoint per Table 3.7-2 in accordance with the Inservice Testing Program. Following testing, lift settings shall be within + 1 percent.

(1) Required to be performed only in MODE 1.

(2) Required to be performed only in MODES 1 and 2.

BEAVER VALLEY - UNIT 13/7-AmnetNo253/4 7-1 Amendment No. 275

TABLE 3.7-1 OPERABLE Main Steam Safety Valves versus Maximum Allowable Power NUMBER OF OPERABLE MSSVs MAXIMUM4 ALLOWABLE POWER PER STEAM GENERATOR (% RTP) 4 < 50 3 < 34 2 < 19 BEAVER VALLEY - UNIT 1 3/4 7-2 Amendment 14o.. 275 (next page is 3/4 7-4)

TABLE 3.7-2 STEAM-LINE SAFETY VALVES PER LOOP LIFT SETTING ORIFICE VALVE NUMBER LIFT SETTING*** TOLERANCES DIAMETER

a. SV-MS1O1A, B & C 1075 psig +1%/-3% 4.250 in.

b. SV-MS1O2A, B & C 1085 psig +/-3% 4.515 in.

C. SV-MS1Q3A, B & C 1095 psig +/-3% 4.515 in.

d. SV-MS1Q4A, B & C 1110 psig +/-3% 4.515 in.

e. SV-MS1Q5A, B & C 1125 psig +/-3% 4.515 in.

The Lift Setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.

BEAVER VALLEY - UNIT 13/7- 3/4 7-4 enetN.27 No. 275 Amendment

PLANT SYSTEMS PRIMARY PLANT DEMINERALIZED WATER (PPDW)

LIMITING CONDITION FOR OPERATION 3.7.1.3 The primary plant demineralized water storage tank shall be OPERABLE with a minimum usable volume of 130,000 gallons.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

With the PPDW storage tank water volume not within the limit, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months either:

a. Restore the water volume to within the limit or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , or

b. Demonstrate the OPERABILITY of the reactor plant river water system as a backup supply to the auxiliary feedwater pumps and restore the PPDW storage tank water volume to within its limit within 7 days or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REQUIREMENTS 4.7.1.3 The PPDW storage tank shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying the water level.

BEAVER VALLEY - 314 7-7 UNIT 13/77AmnetNo25 Amendment No. 275

PLANT SYSTEMS ACTIVITY LIMITING CONDITION FOR OPERATION 3.7.1.4 The specific activity of the secondary coolant system shall be *: 0.10 pCi/gram. DOSE EQUIVALENT 1-131.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

With the specific activity of the secondary coolant system

> 0.10 pCi/gram, bOSE EQUIVALENT 1-131, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.7.1.4 The specific activity of the secondary coolant system shall be determined to be within the limit by performance of the sampling and analysis program of Table 4.7-2.

BEAVER VALLEY - UNIT I 3/4

/ 7-8

- mnmn Amendment No. 7 o 275

- 3a -

transactions shall have no effect on the license for the BVPS Unit 2 facility throughout the term of the license.

(b) Further, the licensees are also required to notify the NRC in writing prior to any change in: (i) the term or conditions of any lease agreements executed as part of these transactions; (ii)the BVPS Operating Agreement, (iii) the existing property insurance coverage for BVPS Unit 2, and (iv) any action by a lessor or others that may have adverse effect on the safe operation of the facility.

C. This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations set forth in 10 CFR Chapter 1 and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level FENOC is authorized to operate the facility at a steady state reactor core power level of 2900 megawatts thermal.

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 156 ,and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license. FENOC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

Amendment No. 156

1.0 DEFINITIONS DEFINED TERMS 1.1 The DEFINED TERMS of this section appear in capitalized type and are applicable throughout these Technical Specifications.

THERMAL POWER 1.2 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

RATED THERMAL POWER 1.3 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant as specified in the Licensing Requirements Manual, and shall not exceed 2900 MWt.

OPERATIONAL NODE 1.4 An OPERATIONAL MODE shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.1.

ACTION 1.5 ACTION shall be those additional requirements specified as corollary statements to each principal specification and shall be part of the specifications.

OPERABLE - OPERABILITY 1.6 A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s). Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electric power sources, cooling -or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function(s) are also capable of performing their related safety function(s).

REPORTABLE EVENT 1.7 A REPORTABLE EVENT shall be 'any of those conditions specified in Section 50.73 to 10 CFR Part 50.

CONTAINMENT INTEGRITY 1.8 CONTAINMENT INTEGRITY shall exist when:

1.8.1 All penetrations required to be closed during accident conditions are either:

a. Capable of being closed by an OPERABLE containment automatic isolation valve system, or BEAVER VALLEY - UNIT 2 1-1 Amendment No. 156

2.0 SAFETY LIMITS.

2.1 SAFETY LIMITS REACTOR CORE 2.1.1 The combination of THERMAL POWER, pressurizer pressure, and the highest operating loop coolant temperature (Tavg) shall not exceed the limits specified in the COLR; and the following Safety Limits shall not be exceeded:

2.1.1.1 The departure from nucleate boiling ratio (DNBR) shall be maintained Ž: 1.17 for WRB-1 DNB correlation for Vantage 5H (V5H) fuel assemblies, and Ž: 1.14 for WRB-2M DNB correlation for Robust Fuel Assemblies (RFA).

2.1.1.2 The peak fuel centerline temperature shall be maintained

5 4700 0F.

APPLICABILITY: MODES 1 and 2.

ACTION:

If Safety Limit 2.1.1 is violated, restore compliance and be in HOT STANDBY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

REACTOR COOLANT SYSTEM PRESSURE 2.1.2 The Reactor Coolant System pressure shall not exceed 2735 psig.

APPLICABILITY: MODES 1, 2, 3, 4, and 5.

ACTION:

MODES 1 and 2 Whenever the Reactor Coolant System pressure has exceeded 2735 psig, be in HOT STANDBY with the Reactor Coolant System pressure within its limit within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

MODES 3, 4, and 5 Whenever the Reactor Coolant System pressure has exceeded 2735 psig, reduce the Reactor Coolant System pressure to within its limit within 5 minutes.

BEAVER VALLEY - UNIT 22-AmnetNo16 2-1 Amendment No. 156

REACTIVITY CONTROL SYSTEMS RefuelingT Water Storage Tank (RWST)

LIMITING CONDITION FOR OPERATION 3.1.2.8 The RWST shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 & 4.

ACTION:

With the refueling water storage tank inoperable, restore the tank to OPERABLE status within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.1.2.8 The RWST shall be verified OPERABLE:

a. At least once per 7 days by:

1. Verifying the boron concentration is between 2400 and 2600 ppm, and

2. Verifying a minimum usable volume of 859,248 gallons.

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the RWST solution temperature is Ž! 45*F and *5 65*F when the RWST ambient air temperature is < 45'F or > 65'F.

BEAVER VALLEY - UNIT 2 3/4 1-15 Amendment No. 156 (Next page is-3/4 1-17)

TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUJMENTATION~

MINIMUM TOTAL NO. CHANNELS CHANNELS ALLOWABLE APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE VALUE MODES ACTION

1. Manual Reactor Trip 2 I 2 N.A. 1, 2, 3(3), 12 4(3) an (3)

2. Power Range, Neutron Flux

a. High Setpoint. 4 2 3 *ý 109.5% of RTP* 1, 2 2

b. Low Setpoint 4 2 3 *525.5% OF RTP* 1(1) , 2 1, 2

3. Power Range, Neutron Flux 4 2 3 *5 5.5% of RTP* 2 High Positive Rate with a time constant

Ž2 seconds

4. DELETED I (3)

5. intermediate Range, 2 1 2 *27.9% of RTP* 3 4 (3) and 5(3)

Neutron Flux (8)

6. Source Range ,Neutron Flux

a. With Rod Withdrawal 2 1 2 *ý 1.3 x 10 5cps 2(2) 3(3), 4 2 (3 3 ,(3)

Capability 4(3 and 5

b. With All Rods Fully 2 0 1 N.A. 3 (9) (9) 5 Inserted and Without Rod and5X Withdrawal Capability

-RATED THERMAL POWER (8) Alternate detectors may only be used for monitoring purposes Without Rod Withdrawal Capability until detector functions are modified to permit equivalent alarm and trip functions.

BEAVER VALLEY - UNIT 2343-AmnetNo16 3/4 3-2 Amendment No.156

TABLE 4.3-1 REACTOR'TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS Channel Nodes in Which Channel Channel Functional Surveillance Functional Unit Check Calibration Test Recru ired

1. Manual Reactor Trip N.A. N.A. 1 2 3 (14) 4t14) : 5 (14)

2. Power Range, Neutron Flux

a. High Setpoint S D() 1(3) Q 1, 2 and Q

b. Low Setpoint S R (6 ) 1,2 6

3. Power Range, Neutron Flux, N.A. R( ) Q 1, 2 High Positive Rate

4. DELETED

5. Intermediate Range, Neutron S R (6 ) 1 2 3 (14)

Flux

6. Source Range~'~ Neutron Flux

a. With Rod Withdrawal S R (6 ) Q'(8) 2, 3 (14) 4 (14)

Capability and 5 (141

b. With All Rods Inserted S R (6 ) Q(8) 3, 4 and 5 and Without Rod Withdrawal Capability

7. Overtemperature AT S R (6 ) Q 1, 2

8. Overpower AT S R Q 1, 2

9. Pressurizer Pressure-Low S R Q 1, 2 (Above P-7)

10. Pressurizer Pressure-High S R Q 1, 2

11. Pressurizer Water Level-High S R Q 1, 2 (Above P-7)

BEAVER VALLEY - UNIT 2 3/4 3431 3-10 Amendment mnmn No.156 o.5

REACTOR COOLANT SYSTEM 3/4.4.3 SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.4.3 All pressurizer code safety valves shall be OPERABLE with a lift setting* of 2485 psig + 1.6% - 3%.**

APPLICABILITY: MODES 1, 2, and 3, MODE 4 with all RCS cold leg temperatures > the enable temperature specified in the PTLR.

ACTION:

a. With one pressurizer code safety valve inoperable, either restore the inoperable valve to OPERABLE status within 15 minutes or be -in HOT SHUTDOWN with any RCS cold leg temperature *5 the enable temperature specified in the PTLR and apply RCS overpressure protection requirements in accordance with Specification 3.4.9.3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b. After any pressurizer code safety valve lift, as indicated by the safety valve position indicator, involving loop seal or water discharge; be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in HOT SHUTDOWN with any RCS cold leg temperature *5 the enable temperature specified in the PTLR and apply RCS overpressure protection requirements in accordance with Specification 3.4.9.3 within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.4.3 No additional requirements other than those required by

.Specification 4.0.5.

The lift setting shall correspond to ambient conditions. of the valve at nominal operating temperature and pressure.

- Within +/- 1% following pressurizer code safety valve testing.

BEAVER VALLEY - UNIT 23/4-AenmtNo16 3/4 4-9 Amendment No.1%

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continiued)

4. Percent Degrradation means the percentage of the tube or sleeve wall thickness affected or removed by degradation.

5. Defect means an imperfection of such severity that it exceeds the plugging or repair limit. A tube containing a defect is defective. Any tube which does not permit the passage of the eddy-current inspection probe shall be deemed a defect~ve tube.

6. Pluggaing or Repair Limit means the imperfection depth at or beyond which the tube shall be removed from service by plugging or repaired by sleeving in the affected area because it may become unserviceable prior to the next inspection. The plugging or repair limit imperfection depths are specified in percentage of nominal wall thickness as follows:

a) original tube wall 40%

This definition does not apply to tube support plate intersections for which the voltage-based repair criteria are being applied. Refer to 4.4.5.4.a.10 for the repair limit applicable to these intersections.

b) ABB Combustion Engineering TIG welded 27%

sleeve wall c) Westinghouse laser welded sleeve wall 25%

7. Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural integrity in. the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steamline or feedwater line break as specified in 4.4.5.3.c, above'.

8. Tube Inspection means an inspection of the steam generator tube from the point of entry (hot-leg side) completely around the U-bend to the top support to the cold-leg.

BEAVER VALLEY - UNIT 23/4-aAenetNo16 3/4 4-14a Amendment No. 156

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

9. Tube Repair refers to sleeving which is used to maintain a tube in-service or return a tube to service. This includes the removal of plugs that were installed as a corrective or preventive measure. The following sleeve designs have been found acceptable:

a) ABB Combustion Engineering TIG welded sleeves, CEN-629-P, Revision 02 and CEN-629-P Addendum 1.

b) Westinghouse laser welded sleeves, WCAP-13483, Revision 2.

10. Tube Support Plate Pluggcingr Limit is used for the disposition of an alloy 600 steam generator tube for continued service that is experiencing predominantly axially oriented outside diameter stress corrosion cracking confined within the thickness of the tube support plates. At tube support plate intersections, the plugging (repair) limit is based on maintaining steam generator tube serviceability as described below:

a) Steam generator tubes, whose degradation is attributed to outside diameter stress corrosion cracking within the bounds of the tube support plate with bobbin voltages less than or equal to

ý2.0 volts will be allowed to remain in service.

b) Steam generator tubes, whose degradation is attributed to outside diameter stress corrosion cracking within the bounds of the tube support plate with a bobbin voltage greater than 2.0 volts will be repaired or plugged, except as noted in 4.4.5.4.a.10.c below.

BEAVER VALLEY - UNIT 2344-bAmnetNo16 3/4 4-14b Amendment No. 156

3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)

ACCUJMULATORS LIMITING CONDITION FOR OPERATION 3.5.1 Each Reactor Coolant System accumulator shall be OPERABLE with:

a. The isolation valve open,

b. Between 6898 gallons and 8019 gallons of usable borated water,

c. .Between 2300 and 2600 ppm of boron, and

d. A nitrogen cover-pressure of between 611 and 685 psig.

APPLICABILITY: MODES 1, 2 and 3.*

ACTION:

a. With one accumulator inoperable due to boron concentration not within limits, restore the inoperable accumulator to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

b. With one accumulator inoperable for reasons other than Action a, restore the inoperable accumulator to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

C. With either Action a or b not being completed within the specified completion time, be in at least HOT STANDBY within the next 6.hours and reduce pressurizer pressure to

<5 1000 psig within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REQUIREMENTS 4.5.1 Each accumulator shall be demonstrated OPERABLE:

a. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by:

1. verifying the usable borated water volume and nitrogen cover-pressure in the tanks are within limits, and

2. Verifying that each accumulator isolation valve is open.

Pressurizer Pressure above 1000 psig.

BEAVER VALLEY - UNIT 23/5- 3/4 5-1 enetNo16 No. 156 Amendment

EMERGENCY CORE COOLINGSYSTEMS 3/4.5.4 SEAL INJECTION FLOW LIMITING CONDITION FOR OPERATION 3.5.4 Reactor coolant pump seal injection flow shall be less than or equal to 28 gpm. with the charging pump discharge pressure greater than or equal to 2457 psig and the seal injection flow control valve I full open.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

a. With the seal injection flow not within the limit, adjust manual seal injection throttle valves to give a flow within the limit with the charging pump discharge pressure greater than or equal to 2457 psig and the seal injection flow I control valve full open within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REQUIREMENTS 4.5.4 Verify at least once per 31 days that the valves are adjusted to give a flow within the limit with the charging pump discharge at greater than or equal to 2457. psig and the seal I injection flow control valve full open. (1)

(1) Not required to be performed until 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after the Reactor Coolant System pressure stabilizes at greater than or equal to 2215 psig and less than or equal to 2255 psig.

BEAVER VALLEY - UNIT 23/5-Amn 3/4 5-7 etNo.5 Amendment No.156

3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE MAIN STEAM SAFETY VALVES (MSSVs)

LIMITING CONDITION FOR OPERATION 3.7.1.1 Five MSSVs per steam generator shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

-- -- ------------ GENERAL NOTE--------------------------- ----

Separate ACTION entry is allowed for each MSSV.

a. With one or more steam generators with one MSSV inoperable and the Moderator Temperature Coefficient (MTC) zero or negative at all power levels, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months reduce THERMAL POWER to less than or equal to 57% RTP; otherwise, be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. With one or more steam generators with two or more MSSVs inoperable, or with one or more steam generators with one MSSV inoperable and the MTC positive at any power level, within 4 -hours reduce THERMAL POWER to less than or equal to the Maximum Allowable % RTP specified in Table 3.7-1 for the number of OPERABLE MSSVs, and reduce the Power Range Neutron Flux-High reactor trip setpoint to less than or equal to -the Maximum Allowable % RTP specified in Table 3.'7-1 (for the number of OPERABLE MSSVs within the next 32

).

(1us otherwise, be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

C. With one or more steam generators with four or more MSSVs inoperable, within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months be in HOT STANDBY and in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS

.4.7.1.1 Verify (2) each required MSSV lift setpoint per Table 3.7-2 in accordance with the Inservice Testing Program. Following testing, lift settings shall be within + 1 percent.

(1) Required to be performed only in MODE 1.

(2) Required to be performed only in MODES 1 and 2.

BEAVER VALLEY - UNIT 2 3/4 7-1 Amendment No. 156

TABLE 3.7-1 OPERABLE Main Steam Safety Valves versus Maximum Allowable Power NUMBER OF OPERABLE MSSVs MAXIMUM ALLOWABLE POWER PER STEAM GENERATOR (% RTP) 4 < 50 3 < 34I 2 < 19I BEAVER VALLEY - UNIT 23/7-AenenNo16 3/4 7-2 Amendment No.1%

TABLE 3.7-2 STEAM LINE SAFETY VALVES PER LOOP LIFT SETTING ORIFICE VALVE NUMBER LIFT SETTING* TOLERANCES DIAMETER

a. 2MSS-SVlO1A, B & C 1075 psig 4.515 in.

+/-31%/3

b. 2MxSS-SV1O2A, B & C 1085 psig 4.515 in.

+/-3 %

C. 2MSS-SV1O3A, B & C 1095 psig 4.515 in.

+/-3%

d. 2MSS-SVJ.04A, B & C 1110 psig 4.515 in.

+/-3%

e. 2MSS-SVlO5A, B & C 1125 psig 4.515 in.

The lif t setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.

BEAVER VALLEY - UNIT 2347-AmnetNo153/4 7-3 Amendment No. 156

PLANT SYSTEMS PRIMARY PLANT DEMINERALIZED WATER (PPDW)

LIMITING CONDITION FOR OPERATION 3.7.1.3 The primary plant demineralized water storage tank shall be OPERABLE with a minimum usable volume of 130,000 gallons.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

With the PPDW storage tank water volume not within the limit, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months either:

a. Restore the water volume to within the limit or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , or

b. Demonstrate the OPERABILITY of the service water system as a backup supply to the auxiliary feedwater pumps and restore the PPDW soaetank water volume to within its limit within 7 days or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REQUIREMENTS 4.7.1.3 The PPDW storage tank shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying the water level.

BEAVER VALLEY - UNIT 2 3476AedetN 3/4 7-6 5 Amendment No. 156

ADMINISTRATIVE CONTROLS REPORTING REQUIREMENTS (Continued)

WCAP-8745-P-A, "Design Bases for the Thermal Overtemperature AT and Thermal Overpower AT Trip Functions," September 1986.

WCAP-12945-P--A, Volume 1 (Revision 2) and Volumes 2 through 5 (Revision 1), "Code 'Qualification Document for Best Estimate LOCA Analysis," March 1998. (Westinghouse Proprietary).

WCAP-10216-P--A, Revision 1A, "Relaxation of Constant Axial Offset Control-FQ Surveillance Technical Specification,"

February 1994.

WCAP-14565-P-A, "VIPRE-Ol Modeling and Qualification for Pressurized Water Reactor Non-LOCA Thermal-Hydraulic Safety Analysis," October 1999.

WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Reference Core Report," April 1995 (Westinghouse Proprietary).

WCAP-15025-P-A, "Modified WRB-2 Correlation, WRB-2M, for Predicting Critical Heat Flux in 17x17 Rod Bundles with Modified LPD Mixing Vane Grids," April 1999.

As described in reference documents listed above, when an initial assumed power level of 102% of rated thermal power is specified in a previously approved method, 100.6% of rated thermal power may be used when input for reactor thermal power measurement of feedwater flow is by the leading edge flow meter (LEFM).

Caldon, Inc. Engineering Report-BOP, "Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFM)/PM System," Revision 0, March 1997.

Caldon, Inc. Engineering Report-160P, "Supplement to Topical1 Report ER-SOP: Basis for a Power Uprate With the LEFM 'System," Revision 0,, May 2000.

BEAVER VALLEY - UNIT 26-0AedntN.5 6-20 Amendment No. 156

v t e Letter Sequence Approval
TAC:MC4645, (Approved, Closed) TAC:MC4646, (Approved, Closed)
Initiation Request, Request, Request, Request, Request Acceptance, Acceptance, Acceptance Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement Administration Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance Meeting, Meeting, Meeting, Meeting Questions 11 March 2005 5 May 2005 2 August 2005 30 September 2005 1 November 2005 Answers 6 September 2005 Results Approval, Approval, Approval Other: ML060330262, ML061770605
MONTHYEAR2005-07-28 [Table View]

ML062020066

Text

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