Text

Amends 223 & 99 to Licenses DPR-66 & NPF-73,respectively, Revising TS 3/4.7.1.1 & Associated Bases for Both Units Re Max Allowable Reactor Power Level Based on Number of Operable MSSVs
	ML20195C829
Person / Time
Site:	Beaver Valley
Issue date:	06/03/1999
From:	Bajwa S; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML20195C838	List: ML20195C829; ML20195C840;
References
	NUDOCS 9906090004
	Download: ML20195C829 (28)
	v • d • e

l%

gar.rog AS, UNITED STATES ye g

g NUCLEAR REGULATORY COMMISSION l

t WASHINGTON, D.C. 20555-0001 j

\\*****p$

l DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY j

PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLEY P'OWER STATION. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 223 License No. DPR-66 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Duquesne Light Company, et al. (the licensee) dated July 9,1998, as supplemented March 31,1999, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I;

{

B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the act?vities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

I L

)

9906090004 990603 fDR ADOCK 05000334 PDR

m-2 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-66 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 223, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 60 days.

FOR THE NUCLEAR REGULATORY COMMISSION 4

S. Singh Bajwa, Chief, Section 1 Project Directorate i Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications l

Date of issuance: June 3,1999 t

m

-N ATTACHMENT TO LICENSE AMENDMENT NO. 223 FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 Replace the following pages of Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginallines indicating the areas of change.

Remove insert Vil Vll 1

X11 Xil XVil XVil 3/4 7-1 3/4 7-1 3/4 7-2 3/4 7-2 3/4 7-3 3/4 7-4 3/4 7-4 8 3/4 7-1 8 3/4 7-1 B 3/4 7-1a B 3/4 7-1b B 3/4 7-1c B 3/4 7-1d i

B 3/4 7-2 B 3/4 7-2 i

I i

y DPR-66 INDEX

+

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE 3/4.7.1.1 Main Steam Safety Valves (MSSVs)........

3/4 7-1 l

3/4.7.1.2 Auxiliary Feedwater System..............

3/4 7-5 3/4.7.1.3 Primary Plant Demineralized Water (PPDW) 3/4 7-7 3/4.7.1.4 Activity................................

3/4 7-8 3/4.7.1.5 Main Steam Line Isolation Valves........

3/4 7-10 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION..............................

3/4 7-11 3/4.7.3 COMPONENT COOLING WATER SYSTEM..........

3/4 7-12 3/4.7.4 REACTOR PLANT RIVER WATER SYSTEM........

3/4 7-13 3/4.7.5 ULTIMATE HEAT SINK - OHIO RIVER.........

3/4 7-14 3/4.7.6 FLOOD PROTECTION........................

3/4 7-15 i

3/4.7.7 CONTROL ROOM EMERGENCY HABITABILITY SYSTEMS.................................

3/4 7-16 3/4.7.8 SUPPLEMENTAL LEAK COLLECTION AND RELEASE SYSTEM..........................

3/4 7-19 i

3/4.7.9 SEALED SOURCE CONTAMINATION.............

3/4 7-22 3/4.7.12 SNUBBERS................................

3/4 7-26 3/4.7.13 AUXILIARY RIVER WATER SYSTEM............

3/4 7-34 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C.

SOURCES 3/4.8.1.1 Operating...............................

3/4 8-1 3/4.8.1.2 Shutdown................................

3/4 8-5 BEAVER VALLEY - UNIT 1 VII Amendment No. Z?3

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DPR-66 INDEX BASES

{

SECTION PAGE i

3/4.7 PLANT SYSTEMS i

~3/4.7.1 TURBINE CYCLE i

3/4.7.1.1 Main Steam Safety-Valves (MSSVs)........

B 3/4 7-1 l

i 3/4.7.1.2 Auxiliary Feedwater System..............

B 3/4 7-2

'3/4.7.1.3-Primary Plant Demineralized Water.......

B 3/4 7-2j 3/4.7.1.4 Activity................................

B 3/4 7-3 3/4.7.1.5 Main Steam Line Isolation Valves........

B 3/4 7-3 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION..............................

B 3/4 7-4 3/4.7.3 COMPONENT COOLING WATER SYSTEM..........

B 3/4 7-4 3/4.7.4 RIVER WATER SYSTEM......................

B 3/4 7-4 3/4.7.5 ULTIMATE HEAT SINK......................

B 3/4 7-4 3/4.7.6 FLOOD PROTECTION........................

B 3/4 7-4 3/4.7.7 CONTROL ROOM EMERGENCY HABITABILITY SYSTEM..................................

B 3/4 7-5 3/4.7.8 SUPPLEMENTAL LEAK COLLECTION AND RELEASE SYSTEM..........................

B 3/4 7-5 j

3/4.7.9 SEALED SOURCE CONTAMINATION.............

B 3/4 7-5 3/4.7.12 SNUBBERS................................

B 3/4 7-6 3/4.7.13-AUXILIARY RIVER WATER SYSTEM............

B 3/4 7-7 3/4.8 FTRCTRICAL POWER ~ SYSTEMS 3/4.8.1 AND 3/4.8.2 A.C. SOURCES, D.C.

SOURCES AND ONSITE POWER DISTRIBUTION SYSTEMS.......

B 3/4 8-1 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION.....................

B 3/4 9-1 3/4.9.2

-INSTRUMENTATION.........................

B 3/4 9-1 BEAVER VALLEY - UNIT 1 XII Amendment No.28

7 DPR-66 Table Index-(cont.)

TABLE

-TITLE PAGE 3.3 Accident Monitoring Instrumentation 3/4 3-51 4.3-7 Accident Monitoring Instrumentation 3/4 3 Surveillance Requirements 3.3-13 Explosive Gas Monitoring Instrumentation 3/4 3-55 4.3-13 Explosive Gas Monitoring Instrumentation 3/4 3-57 Surveillance Requirements 4.4-1 Minimum Number of Steam Generators to be 3/4 4-10g Inspected During Inservice Inspection 4.4-2 Steam Generator Tube Inspection 3/4 4-10h 4.4-3 Reactor Coolant System Pressure Isolation 3/4 4-14b Valves 3.4-1 Reactor Coolant System Chemistry Limits 3/4 4-16 4.4-10 Reactor Coolant System Chemistry Limits 3/4 4-17 Surveillance Requirements 4.4-12 Primary Coolant Specific Activity Sample 3/4 4-20 and Analysis Program 3.7-1 OPERABLE Main Steam Safety Valves versus 3/4 7-2 Applicable Power in Percent of RATED THERMAL POWER (RTP) 3.7-2 Steam Line Safety Valves Per Loop 3/4 7-4 4.7-1 Snubber Visual Inspection Interval 3/4 7-31 4.7-2 Secondary Coolant System Specific Activity 3/4 7-9 Sample and Analysis Program 3.8-1 Battery Surveillance Requirements 3/4 8-9a 3.9-1 Beaver Valley Fuel Assembly Minimum Burnup 3/4 9-15 vs. Initial _U235 Enrichment For Storage in Region 2 Spent Fuel Racks BEAVER VALLEY - UNIT 1 XVII Amendment No.ZB

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, DPR-66 3/4.7= PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE-MAIN STEAM SAFETY VALVES'(MSSVs) l LIMITING CONDITION FOR OPERATION L3. 7.1.1' The MSSVs shall'be OPERABLE as specified in Table 3.7-1 and Table 3.7-2.

APPLICABILITY:. MODES 1, 2 and 3.

ACTION:

- - - - - - --- - - - - - - GENERAL NOTE 4.

Separate ACTION entry is allowed for each MSSV'.

a.

With one or more required MSSVs inoperable, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months reduce - power to.'less than or equal to the applicable percent RATED THERMAL POWER listed in Table 3.7-1; 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 j

HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

i b.

With one-or more steam ~ generators with less than two MSSVs OPERABLE. 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 .

c.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS NI 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 MODES 1 and 2.

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

I *.

DPR-66 TABLE 3.7-1 OPERAB.LE Main Steam Safety Valves versus Applicable Power in Percent of RATED THERMAL POWER (RTP)

MINIMUM NUMBER OF MSSVs PER STEAM GENERATOR APPLICABLE POWER REQUIRED OPERABLE

(% RTP)

)

5 S 100 4

4 5 57 3

g 39 2

5 22 I

J i

i BEAVER VALLEY - UNIT 1 3/4 7-2 Amendment No.223 (next page is 3/4 7-4) l

DPR-66 TABLE 3.7-2 l

-STEAM LINE SAFETY VALVES PER LOOP LIFT SETTING ***

ORIFICE VALVE NUMBER

(+1% -3%)

DIAMETER l

a.

SV-MS101A, B&C 1075 psig 4.250 in.

b.

SV-MS102A, B&C 1085 psig 4.515 in.

c.

SV-MS103A,_B & C 1095 psig 4.515 in.

d.

SV-MS104A, B&C 1110 psig 4.515 in.

e.

SV-MS105A, B&C 1125 psig 4.515 in.

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

BEAVER VALLEY - UNIT 1 3/4 7-4 Amendment No. Z?3

n.

6 DPR-66 3/4;7 PLANT-SYSTEMS BASES 3/4.7.1 TURBINE CYCLE 3/4.7.1.1 MAIN STEAM SAFETY VALVES (MSSVs)

BACKGROUND The primary ' purpose of - the main steam safety valves (MSSVs) is to provide overpressure protection for the secondary system.

The MSSVs also provide protection against overpressurizing the reactor coolant pressure boundary (RCPB) by.providing a heat sink for the removal of.

energy' from the Reactor Coolant System (RCS) if the preferred heat sink, provided by the condenser and circulating Water System, is not available.

Five MSSVs are located on each main steam

header, outside

. containment, upstream of the main steam isolation

valves, as

. described -in the UFSAR, Section ' 10. 3.1.

The specified valve lift settings and relieving capacities are in accordance with the requirements - of Section III of the ASME Boiler and Pressure Code, 1971 Edition.

The total relieging capacity for all valves on all of

.the steam lines is 12.8 x 10 lbs/hr which is 110 percent of the s

total secondary steam flow of 11.7 x 10 lbs/hr at 100% RATED THERMAL POWER..

The MSSV design includes staggered setpoints, according to Table 3.7-2 in the; accompanying limiting condition for operation (LCO),_ so that only _ the needed valves will actuate.

Staggered setpoints reduce the potential for valve' chattering that is due to steam pressure insufficient to fully open all valves following a turbine reactor trip.

APPLICABLE SAFETY ANALYSES The design basis for the MSSVs comes from the ASME Code,Section III i

and its purpose is-to limit-the secondary system pressure to less than or ' equal to 110 percent of design pressure when passing 100 percent of design' steam flow.

This design basis is sufficient to cope with any anticipated operational occurrence (AOO) or accident considered in the Design Basis Accident (DBA) and transient analysis.

The events that challenge the relieving capacity of the MSSVs, and thus RCS pressure, are those characterized as decreased heat removal events, which are presented in UFSAR, Section 14.1.

Of these, the full power turbine trip without steam dump is the limiting AOO.

This event also terminates normal feedwater flow to the steam generators.

The transient response for turbine trip without a direct reactor trip presents no' hazard to the integrity of the RCS or the Main Steam System.

If a minimum reactivity feedback is assumed, the reactor is BEAVER VALLEY - UNIT-1.

B 3/4 7-1 Amendment No.223

( ).

DPR-66 li PLANT SYSTEMS" BASES MAIN STEAM SAFETY VALVES (MSSVs) (Continued)

APPLICABLE SAFETY ANALYSES (Continued) i tripped on-high pressurizer pressure.

In this case, the pressurizer safety valves open, and RCS pressure remains below 110 percent of the design value.

The MSSVs also open to limit the secondary steam pressure.

If maximum reer::tivity feedback is assumed, the reactor is tripped on overtemperature AT.

The departure from nucleate ~ boiling ratio increases lthroughout the transient, and never drops below its initial value.

Pressurizar relief valves'and MSSVs are activated and prevent overpressurization in the primary and secondary systems.

The MSSVs are assumed to have two active and one passive failure modes.

The active failure modes are spurious opaning, and failure to reclose once opened.

The passive failure mode is failure to open upon demand.

LfJ2 The accident analysis requires four MSSVs per steam generator to i

provide overpressure protection for design basis transients occurring at 102' percent RATED THERMAL POWER (RTP).

An MSSV will be considered inoperable if it fails to open on demand.

The LCO requires that five MSSVs be OPERABLE in compliance with the ASME Code,Section III, even though this is not a requirement of the DBA analysis.

This is because operation with less than the full number of MSSVs requires limitations on allowable THERMAL

-POWER (to meet ASME Code requirements). 'These limitations are according to Table 3.7-1 in the accompanying LCO and associated ACTION.

The OPERABILITY of the MSSVs.is defined as the ability to open within the setpoint tolerances, relieve steam generator overpressure, and resent when pressure has been reduced.

The OPERABILITY of the MSSVs

'is determined by periodic surveillance testing in accordance with the Inservice Testing Program.

The lift settings, according to Table 3.7-2 in the accompanying LCO, correspond to ambient conditions of the valve at nominal operating temperature and pressure, as identified by a note.

This -LCO: provides assurance that the MSSVs, will perform their designed safety functions to mitige,te the consequences of accidents that could result in a. challenge to the RCPB.

BEAVER VALLEY - UNIT 1 B 3/4 7-la Amendment No.223

,-n e

DPR-66 PLANT SYSTEMS BASES MAIN STEAM SAFETY VALVES (MSSVs) (Continued)

APPLICABILITY

~

In MODE 1 above 22% RTP, the number of MSSVs per steam generator required to be OPERABLE must be according' to Table 3.7-1 in the accompanying LCO..

In MODE 1 below 22% RTP and in MODES 2 and 3 only two MSSVs per steam generator are required to be OPERABLE.

In MODES 4 and 5, there are no credible transients requiring the MSSVs.-

The steam generators are not normally used for heat removal

{

in MODES 5 and 6,

and thus cannot be overpressurized; there is no i

requirement for the MSSVs to be OPERABLE in these MODES.

ACTION The ACTIONS are modified by a General Note indicating that separate condition entry is allowed for each MSSV.

a.

With one or more MSSVs inoperable, reduce power so that the available MSSV relieving capacity meets the ASME

Code,Section III requirements for the applicable THERMAL POWER.

Operation with less than all five MSSVs OPERABLE for each steam generator is permissible, if THERMAL POWER is proportionally limited to the relief capacity of the remaining MSSVs.

This is accomplished by restricting THERMAL POWER so that the energy transfer to the' most limiting steam generator is not greater than the available relief capacity in that steam generator.

The THERMAL POWER is limited by the governing ' equation in the relationship q

mAh, where q is the heat input from the

=

primary side, m is the steam flow rate and Ah is the heat of vaporization at the steam relief pressure (assuming no subcooled feedwater).

For each steam generator, at a specified pressure, the fractional power level (FPL) is determined as follows:

FPL = '90/Q 9

K i

I

)

l BEAVER VALLEY - UNIT 1 B 3/4 7-lb Amendment No.223 i

J

i DPR-66 PLANT SYSTEMS BASES MAIN STEAM SAFETY VALVES (MSSVs) (Continued) i ACTION (Continued) where:

FPL Fraction of RATED THERMAL POWER equivalent to the

=

safety analysis limit minus 9 percent (to account for typical instrument and channel uncertainties).

The uncertainty ensures the maximum plant operating power level will then be lower than the safety analysis limit by an appropriate operating margin.

Nominal NSSS power rating of the plant (including Q

=

reactor coolant pump heat), Mwt (Btu /sec)

Conversion factor, 947.82 K

=

Mwt Minimum total steam flow rate capability of the w.

=

operable MSSVs on any one steam generator at the highest MSSV opening pressure including tolerance j

and accumulation, as appropriate, in lb/sec.

For

example, if the maximum number of inoperable MSSVs on any one steam generator is one, then w.

should. be a summation of the capacity of the operable MSSVs at the highest operable MSSV operating

pressure, excluding the highest capacity MSSV.

If the maximum number of inoperable MSSVs per steam generator is three then w should be a summation of the capacity of the operable MSSVs at the highest operable MSSV operating pressure, excluding the three highest capacity MSSVs.

hrg Heat of vaporization for steam at the highest

=

MSSV opening pressure including tolerance and accumulation, as appropriate, Btu /lbm Number of loops in plant N

=

BEAVER VALLEY - UNIT 1 B 3/4 7-ic Amendment No. 223 j

r DPR-66 PLANT SYSTEMS BASES MAIN STEAM SAFETY VALVES (MSSVs) (Continued)

ACTION (Continued) b.

If the MSSVs cannot be restored to OPERABLE status within the associated completion time, or if one or more steam generators have less than two MSSVs OPERABLE, the unit must be placed in a MODE in which the LCO does not apply.

To achieve this status, the unit'must be placed in at least MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in MODE 4 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The allowed completion times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.

c.

An exception to Specification 3.0.4 is provided since the above ACTION statements require a shutdown if they are not met within a specified period of time.

SURVEILLANCE REOUIREMENTS (SR)

SR 4.7.1.1 This SR verifies the OPERABILITY of the MSSVs by the verification of each MSSV lift setpoint in accordance with the Inservice Testing Program.

The ASME Code,Section XI, requires that safety and relief valve tests be performed in accordance with ANSI /ASME OM-1-1987.

According to ANSI /ASME OM-1-1987, the following tests are required:

a.

Visual examination; b.

Seat tightness determination; Setpoint pressure determination (lift setting); and c.

d.

Compliance with owner's seat tightness criteria.

The ANSI /ASME Standard requires that all valves be tested every 5 years.

The ASME Code specifies the activities and frequencies necessary to satisfy the requirements.

Table 3.7-2 allows a

+1 percent

-3 percent setpoint tolerance for OPERABILITY; however, the valves are reset to 1 percent during the Surveillance to allow for drift.

BEAVER VALLEY - UNIT 1 B 3/4 7-Id Amendment No. 223

F'.

=.

DPR-66

~

. PLANT SYSTEMS BASES MAIN STEAM SAFETY' VALVES (MSSVs) (Continued)

SURVEILLANCE'REOUIREMENTS (SR) (Continued)

This SR istmodified:by a Note that allows entry into and operation in MODE 3 prior to performing.the SR.

The MSSVs may be either bench tested or tested in situ at hot conditions using an assist device to

' simulate. lift. pressure.

If the MSSVs are not tested-at hot conditions, the lift setting pressure:shall be corrected to ambient conditions'of the valve at operating temperature and pressure.

3/4.7'.1.2 AUXILI'ARY FEEDWATER' SYSTEM (AFW)

BACKGROUND The AFW System automatically supplies feedwater-to the steam generators to' remove decay heat from the Reactor Coolant System upon the loss of normal feedwater supply.

The AFW system consists of two motor driven pumps and one steam turbine driven pump.

The pumps are equipped with independent recirculation lines-to prevent pump

- operation against a closed system.

Each motor driven AFW pump is

_ powered from 'an independent Class 1E power supply and each pump feeds all three steam generators.

The steam turbine driven AFW pump receives steam from two of the three main steam lines upstream of the main' steam isolation valves.

Each of the steam feed lines will supply 100 percent of the-steam requirements for the turbine driven

-AFW pump.

The steam feed. lines from each of the main steam lines combine to form one main header.

The main header then splits-into two - parallel' paths with one Train "A"

operated and ' one Train "B"

operated. isolation valve on each pathway.

These two parallel paths then combine into one header which supplies the turbine driven AFW pump.

The flow path from the domineralized water storage tank (WT-TK-10) to the steam generators consists of individual supply lines to each of the three AFW pumps.

Each motor driven AFW pump has an individual line that connects to its train related supply header.

In addition, each motor driven AFW pump has the ability to be aligned to the opposite train header.

The turbine driven pump has BEAVER VALLEY - UNIT 1 B 3/4 7-2 Amendment No. 223

=.

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[o

-k UNITED STATES j,

.j NUCLEAR REGULATORY COMMISSION

~r WASHING TON, D.C. 20555-0Co1 o

49.....,o DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY

~

THE CLEVELAND ELECTRIC ILLUMINATING COMPANY THE TOLEDO EDISON COMPANY DOCKET NO. 50-412 BEAVER VALLEY POWER STATJON. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 99 License No. NPF-73 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Duquesne Light Company, et al. (the licensee) dated July 9,1998, as supplemented March 31,1999, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

[7 1

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)

'9

~ -

2.'

Accordingly, the license is amended by changes to the Technical Specifications as

' indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating Ucense No. NPF-73 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 99, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license. DLCO shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

i 3.

This license amendment is effective as of the date of its issuance and shall be implemented within 60 days.

FOR THE NUCLEAR REGUL2. TORY COMMISSION S. Singh Bajwa, Chief, Section 1 Project Directorate i Division of Licensing Project Management j

Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance:

June 3,1999 1

s ATTACHMENT TO LICENSE AMENDMENT NO. 09 FACILITY OPERATING LICENSE NO. NPF-73 DOCKET NO. 50-412 Replace the following pages of Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginallines indicating the areas of change.

Remove Insert Vil Vil 3/4 7-1 3/4 7-1 3/4.7-2 3/4 7-2 3-4 7-3 3/4 7-3 8 3/4 7-1 B 3/4 7-1 B 3/4 7-1a B 3/4 7-1b B 3/4 7-1c B 3/4 7-1d B 3/4 7-2 8 3/4 7-2 i

j

.s i

o NPF-73 c

0 INDEX LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.6.4 COMBUSTIBLE GAS CONTROL J

3/4.6.4.1 Hydrogen Analyzers......................

3/4 6-31 i

3/4.6.4.2 Electric Hydrogen Recombiners...........

3/4 6-32 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE 3/4.7.1.1 Main Steam Safety Valves (MSSVs)........

3/4 7-1 l

3/4.7.1.2 Auxiliary Feedwater System..............

3/4 7-4 3/4.7.1.3 Primary Plant Demineralized Water (PPDW) 3/4 7-6 3/4.7.1.4 Activity................................

3/4 7-7 3/4.7.1.5 Main Steam Line Isolation Valves........

3/4 7-9 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION..............................

3/4 7-10 i

3/4.7.3 PRIMARY COMPONENT COOLING WATER SYSTEM..

3/4 7-11 3/4.7.4 SERVICE WATER SYSTEM (SWS)..............

3/4 7-12 3/4.7.5 ULTIMATE HEAT SINK - OHIO RIVER.........

3/4 7-13 3/4.7.6 FLOOD PROTECTION........................

3/4 7-14 3/4.7.7 CONTROL ROOM EMERGENCY AIR CLEANUP AND PRESSURIZATION SYSTEM...................

3/4 7-15 3/4.7.8 SUPPLEMENTAL LEAK COLLECTION AND RELEASE SYSTEM (SLCRS)..........................

3/4 7-18 3/4.7.9 SEALED SOURCE CONTAMINATION.............

3/4 7-20 3/4.7.12 SNUBBERS................................

3/4 7-24 3/4.7.13 STANDBY SERVICE WATER SYSTEM (SWE)......

3/4 7-30 l

BEAVER VALLEY - UNIT 2 VII Amendment No. 99

r

'e NPF-73

' fe '.

'3/4.7 PLANT SYSTEMS 3/4.7.1 -TURBINE CYCLE MAIN STEAM SAFETY VALVES (MSSVs) l LIMITING CONDITION FOR. OPERATION 3.7.1.1 The MSSVs shall be OPERABLE as specified in Table 3.7-1 and-Table 3.7-2.

APPLICABILITY:

MODES 1, 2 and 3.

ACTION:'

- - - - - - - - - - - - - GENERAL NOTE Separate ACTION entry is allowed for each MSSV.

'With one or more required MSSVs inoperable, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months a.

reduce power to less than or equal to the~ applicable percent RATED THERMAL ' POWER-listed in Table-3.7-1; 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 .

Eb..

With-one or more steam' generators with less than two MSSVs OPERABLE 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 .

The provisions of Specification 3.0.4 are not applicable.

.c.

SURVEILLANCE REQUIREMENTS III 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 i l' percent.

I

)

(1)

Required to be performed only in MODES 1 and 2.

BEAVER VALLEY - UNIT 2 3/4 7-1 Amendment No. 99 t

s NPF-73 TABLE 3.7-1 i

OPERABLE Main Steam Safety Valves versus Applicable Power in Percent of RATED THERMAL POWER (RTP)

MINIMUM NUMBER OF MSSVs PER STEAM GENERATOR APPLICABLE POWER REQUIRED OPERABLE

(% RTP) 5 5 100 4

5 58 3

5 41 2

5 24 4

BEAVER VALLEY - UNIT 2 3/4 7-2 Amendment No. 99 i

V NPF-73

'e TABLE 3.7-2 STEAM LINE SAFETY VALVES PER LOOP LIFT SETTING

ORIFICE VALVE-NUMBER

(+1% -3%)

DIAMETER l

a.

2 MSS-SV101A, B&C 1075 psig 4.515 in, b.

2 MSS-SV102A, B&C 1085 psig 4.515 in.

c.

2 MSS-SV103A, B &~C 1095 psig 4.515 in, d.

2 MSS-SV104A, B&C 1110 psig 4.515 in.

e.

2 MSS-SV105A, B&C 1125 psig 4.515 in.

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

1

' BEAVER VALLEY - UNIT 2.

3/4 7-3 Amendment No. 99

c-

-NPF-73' 3/4.7' PLANT SYSTEMS-

' BASES-3/4;7.1' TURBINE CYCLE

'3/4.7.1.1 MAIN STEAM SAFETY VALVES (MSSVs)

BACKGROUND The _ primary purpose of the main steam safety valves (MSSVs) is to provide overpressure protection for the secondary system.

The MSSVs also provida protection against overpressurizing the reactor coolant.

pressure bound:.ry (RCPB) by providing a heat sink for the removal of energy from.the Reactor Coolant System (RCS) if the preferred heat

{

sink, provided by'the condenser and Circulating Water System, is not available.

Five MSSVs are located on each main steam

header, outside f

containment, upstream of the main. steam isolation

valves, as described in the - UFSAR, Section 10.3.2.

The specified valve lift settings and relieving-capacities are in accordance with the requirements of Section III of the ASME Boiler and Pressure Code, 1971 Edition and Winter 1972 Addenda.

The total religving capacity

.for all valves on all of the steam' lines is 12.7 x 10 lbs/gr which 4

' is 110' percent of the total secondary steam flow of 11.6 x'10 lbs/hr at 100% RATED THERMAL. POWER.

.The MSSV design includes staggered i

setpoints, according to Table 3.7-2 in the accompanying limiting

' condition for operation (LCO), - so that. only the needed valves will

-actuate..

Staggered setpoints reduce the potential for. valve chattering that is due to steam pressure insufficient to fully open

{

all valves following a turbine reactor trip.

APPLICABLE SAFETY-ANALYSES-The design basis for the MSSVs comes from the ASME Code,Section III and its purpose is to limit the secondary system pressure to less than or equal to 110 percent of design pressure when passing 100 percent of design steam flow.

. This design basis is sufficient to cope with any anticipated operational occurrence (AOO) or accident considered in the Design Basis Accident (DBA) and transient analysis.

The events that challenge the relieving capacity of the MSSVs, and thus RCS pressure, are those characterized as decreased heat removal events,- which are presented in UFSAR, Section 15.2.

Of these, the full power. turbine trip ~without_ steam dump is the limiting AOO.

This

. event also terminates normal feedwater flow to the steam generators.

The transient' response for turbine trip without a direct reactor trip presents no hazard to the integrity of the RCS or the Main Steam System.

If a minimum reactivity feedback is assumed, the reactor is BEAVER VALLEY - UNIT 2 B 3/4 7-1 Amendment No. 99

s.

NPF _j PLANT SYSTEMS-BASES MAIN STEAM SAFETY VALVES (MSSVal (Continued)

APPLICABLE SAFETY ANALYSES (Continued) tripped on'high pressurizer pressure.

In this case, the pressurizer safety valves open, and RCS pressure remains below 110 percent of the design value.

.The MSSVs also open to limit the ' secondary steam pressure.

If maximum reactivity feedback is assumed, the reactor is tripped on overtemperature AT.

The departure.from nucleate boiling ratio increases throughout the transient, and never drops below its initial e

'value.

Pressurizer relief valves and MSSVs are activated and prevent overpressurization.in the primary and secondary systems.

The MSSVs are assumed'to have two active and one passive failure modes.

The active fail're modes are spurious opening, and failure to reclose u

once opened.

The passive failure mode is failure to open upon demand.

LGQ The ~ accident analysis requires four MSSVs per steam generator to provide overpressure protection for design basis transients occurring at 102 percent RATED THERMAL POWER-(RTP).

An MSSV will be considered inoperable if it fails to open on demand.

The LCO requires that five MSSVs be OPERABLE in compliance with the ASME Code,Section III, even though this is not a requirement of the DBA analysis..

This is because operation with less than the full number of MSSVs requires limitations on allowable THERMAL. POWER (to meet-ASME Code

. requirements).

These limitations are according to Table 3.7-1 in the accompanying LCO and associated ACTION.

The OPERABILITY of the MSSVs is defined as the. ability to open within the setpoint tolerances, relieve steam generator overpressure, and reseat when pressure has been reduced.

The OPERABILITY of the MSSVs is determined by periodic surveillance testing in accordance with the Inservice-Testing Program.

The lift settings, according to Table 3.7-2 in the accompanying LCO, correspond to ambient conditions of the valve at nominal operating temperature'and pressure, as identified by a note.

'This LCO provides assurance that the MSSVs will perform their designed' safety functions to mitigate the consequences of accidents that could result in a challenge'to the RCPB.

BEAVER VALLEY - UNIT 2

.B 3/4 7-la Amendment No. 99

,, N e.

NPF D PLANT SYSTEMS BASES MAIN STEAM' SAFETY VALVES (MSSVs) (Continued)

APPLICABILITY In MODE.1 above 24% RTP, the number of MSSVs per steam generator required to be. OPERABLE must be according to Table 3.7-1 in the accompanying LCO.

In MODE 1 below 24% RTP-and in MODES 2 and 3' only two MSSVs per steam generator are required to.be OPERABLE.

1 In MODES ' 4. and 5, there are no credible transients requiring the MSSVs.

The steam generators are not normally used for heat removal in MODES.5 and 6,

and thus cannot be overpressurized; there. is no requirement for the MSSVs to be OPERABLE in these MODES.

1 ACTION i

The ACTIONS-are modified by a General Note indicating that separate condition entry.is allowed for each MSSV.

a.

With one.or ' more MSSVs inoperable, reduce power so that the available MSSV relieving capacity meets the ASME

Code,Section III. requirements for the applicable THERMAL POWER.

Operation with less than all five MSSVs OPERABLE for each steam generator. is permissible, if. THERMAL POWER is proportionally limited to the relief capacity of-the remaining MSSVs'.

This is accomplished by-restricting THERMAL POWER so that the-energy transfer to the most -limiting steam generator is not greater i

than the available relief capacity in that steam generator.

1 The THERMAL POWER is limited by the governing equation in the relationship q

mAh, where q is the heat input from the

=

primary side, m is the steam flow rate and Ah is the heat of vaporization at the steam relief pressure (assuming no subcooled feedwater).

For each steam generator, at a specified pressure, the fractional power level (FPL) is deter 1 mined as follows:

FPL = 100/Q 9

K I

i I

I BEAVER VALLEY - UNIT 2 B 3/4 7-lb

. Amendment No.99

p i

NPF-73 1

k PLANT SYSTEMS I

BASES MAIN STEAM' SAFETY VALVES (MSSVs) fContinuedi ACTION (Continued) where:

FPL Fraction of RATED THERMAL POWER equivalent to the

=

- safety analysis limit minus 9 percent (to account I

for typical instrument and channel uncertainties).

The uncertainty ensures the maximum plant operating power level will then be lower than the safety analysis limit by an appropriate operating margin.

Nominal NSSS power rating of the plant (including Q

=

reactor coolant pump heat), Mwt (Btu /sec)

K Conversion factor, 947.82

=

Mwt Minimum total steam flow rate capability of the W.

=-

operable MSSVs on any one steam generator at the highest MSSV opening pressure including tolerance and accumulation,.as appropriate, in lb/sec.

For

example, if the maximum. number of inoperable MSSVs on any one steam generator is one, then we should be a summation of the capacity of the operable MSSVs at the highest' operable MSSV operating

pressure, excluding the highest capacity MSSV.

If the maximum number of inoperable MSSVs per steam generator is three then w should be a summation of the capacity of the operable MSSVs at the highest operable MSSV operating -pressure, excluding the three highest capacity MSSVs.

hrg Heat of vaporization for steam at the highest

=

MSSV opening pressure including tolerance and accumulation, as appropriate, Btu /lba

. Number of loops in plant N

=

i BEAVER VALLEY - UNIT 2 B 3/4 7-ic Amendment No. 99

n

.4

e ig.

NPF-73 PLANT SYSTEMS

' BASES MAIN STEAM SAFETY' VALVES (MSSVs) (Continued)

ACTION " (Contiriued1

-b.

If the MSSVs cannot be restored to OPERABLE status within the associated completion time, or if one or more steam generators have less than two MSSVs OPERABLE, the unit must be placed in a MODE in which the LCO does not apply.

To achieveLthis status, the_ unit must be placed in at least' MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in MODE f,

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

The allowed completion times are reasonable,-based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.

c.

LAn exception to Specification 3.0.4 is provided since the above i

ACTION statements require a shutdown if they are not met within a specified period of time.

j SURVEIT TANCE REOUIREMENTS (SR)

~SR 4.7.1.1 This SR. verifies the OPERABILITY-of the MSSVs by the verification of each. MSSV lift setpoint in accordance with the Inservice Testing Program.

The ASME Code,Section XI,' requires that safety and relief valve. tests be performed in' accordance with ANSI /ASME OM-1-1987.

According to ANSI /ASME OM-1-1987, the following tests are required:

a.

. visual examination; b.

Seat tightness determination;.

c.

Setpoint pressure determination (lift setting); and d.

Compliance with owner's seat tightness criteria.

The ANSI /ASME Standard requires that all valves be tested every 5 years.

The ASME Code specifies the activities and frequencies necessary to satisfy the requirements.

Table 3.7-2 allows a

+1 percent

-3 percent setpoint tolerance for OPERABILITY; however, the valves are reset to 1 percent during the Surveillance to allow for drift.

BEAVER VALLEY

. UNIT 2 B 3/4 7-1d Amendment No. go

?

]

c*

..o; NPF-73 i

PLANT SYSTEMS i

i I

BASES 1

MAIN STEAM SAFETY VALVES (MSSV9) (Continued)

EURVEILIANCE REOUIREMENTS (sri (Continued)

This SR is modified by a-Note that allows entry into and operation in MODE 3 prior to performing the SR.

The~MSSVs may be either bench

-tested ~or tested'in situ at hot conditions using an assist device to simulate lift pressure.

If the MSSVs are not tested at hot conditions, the lift setting pressure-shall be corrected to ambient conditions of the valve at operating temperature and pressure.

3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM (AFW)

BACKGROUND The AFW System automatically supplies feedwater to the steam generators to remove decay heat from the Reactor Coolant System upon the loss of normal feedwater supply.

The AFW system consists of two motor driven pumps and one steam turbine driven pump.

The pumps are equipped with independent recirculation lines to prevent pump operation against a closed system.

Each motor driven AFW pump is powered from an independent Class 1E power supply and each pump feeds all three steam generators.

The steam turbine driven AFW pump receives steam from at least two main steam lines upstream of the main steam isolation valves.

Each of the steam feed lines. will supply 100 percent of the steam requirements for the turbine driven AFW pump.

The steam feed. lines from each of.the main steam lines contain two in-line series solenoid operated isolation valves.

Downstream of the series isolation valves, the three lines combine to form one main header.

The main header then supplies the turbine driven AFW pump.

The flow path from the demineralized water storage tank (TK-210) to the steam generators consists of individual supply lines to each of the three AFW pumps.

Each motor driven AFW pump has an individual line.that connects to its train related supply header.

The turbine driven pump has an individual line that can be aligned to either the Train "A"

or "B"

supply header as necessary.

Both the Train "A" and "B" supply headers each contain three normally open remotely operated valves arranged in parallel.

Each of these valves then provides a flow path to one of the three common feedwater injection headers.

Eachfof-the feedwater injection headers then supplies its designated steam generator via the normal feedwater header downstream of the feedwater isolation valves.

The steam generators function as a heat sink for core decay heat.

The heat load is dissipated by releasing steam to the atmosphere from the steam generators via the main steam safety valves (MSSVs) or atmospheric dump valves (ADVs).

If the main condenser is available, steam may be released via the steam dump t

valves.

BEAVER VALLEY.- UNIT 2 B 3/4 7-2

' Amendment No.99

ML20195C829

Text

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