ML20082E421

Amends 196 & 187 to Licenses DPR-77 & DPR-79,respectively. Amends Revise TSs to Reduce High Reactor Power Level Setpoints When One or More Main Steam Safety Valves Inoperable & Incorporate Related Charges

ML20082E421
Person / Time
Site:	Sequoyah
Issue date:	04/04/1995
From:	Hebdon F NRC (Affiliation Not Assigned)
To:
Shared Package
ML20082E426	List: ML20082E421 ML20082E429
References
NUDOCS 9504110221
Download: ML20082E421 (20)

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.)ge 7+f UNITED STATES l

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- NUCLEAR REGULATORY COMMISSION j

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DOCKET NO.'50-327-1 if,gg)YAtLEH;LfAILELANT. UNIT 1 e

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AMENDMENT TO FACILITY OPERATING LICENSE l

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4 Amendment No. 196

1 License No. DPR-77

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

A.

The application for amendment by Tennessee Valley Authority (the -

license)) dated December 16, 1994, and supplemented February 10, 1995, complies with the standards and requirements'of the Atomic Energy At t of 1954, as amended (the Act), and the Commission's rules j

and regul.'tions set forth in 10 CFR Chapter'I; l

o B.

The facility will operate in conformity with the application, the I

provisions of the Act, and the rules.and regulations of the Commission; C.

There is reasonable assurance (1) that.the activities aut'orized by h

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 1

been satisfied.

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9504110221 950404 POR ADOCK 05000327 P

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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-77 is hereby amended to read as follows:

1 (2) Technical Soc.cifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.196, are hereby incorporated in the -

license. The licensee shall operate the facility in accordance with i

the Technical Specifications.

3.

This license amendment is effective as of its date of issuance, to be implemented within 45 days.

FOR THE NUCLEAR REGULATORY COMMISSION

' cte b-Frederick J. He W n, Director Project Directorate II-4 l

Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications I

Date of Issuance: April 4, 1995 i

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- Accordingly, the license is amended by changes to the Technical l

Specifications as indicated in the attachment to this license amendment-and paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby amended to read as follows:-

(2) Technical Soecifications t

The Technical Specifications contained in Appendices-A and B, as revised through Amendment No.

, 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 its date of issuance, to be implemented within 45 days..

FOR THE NUCLEAR REGULATORY ComISSION LLA IddL Frederick J.~Hebdo, Director Project Directorate II-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: April 4, 1995 1

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ATTACHMENT TO LICENSE AMENDMENT N0.187 l

FACILITY OPERATING LICENSE NO. DPR-79 DOCKET NO. 50-328 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change. Sp111over page is provided to maintain document completeness.

REMQYE INSERT 3/4 7-1 3/4 7-1 I

3/4 7-2 3/4 7-2 3/4 7-3 3/4 7-3 3/4 7-4 3/4 7-4 B3/4 7-1 B3/4 7-1 83/4 7-2 B3/4 7-2 B3/4 7-2a B3/4 7-2a*

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3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.7.1.1 Main steam safety valves (MSSVs) shall be OPERABLE with lift settings as specified in Table 3.7-2.

APPLICABILITY: MODES 1, 2 and 3*.

ACTION:

a.

With one or more MSSVs inoperable, operation may proceed provided, that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable v.ilve is restored to OPERABLE status or the Power Range Neutron Flux High Setpoint trip is reduced per Table 3.7-1.

The provisions of Specification 3.0.4 are not applicable.

b.

With the requirements of ACTION a., not met or with one or more steam generators with less than two MSSVs OPERABLE be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN in the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REOUIREMENTS 4.7.1.1 No additional Surveillance Requirements other than those required by Specification 4.0.5.

• With the reactor trip system breakers in the closed position.

l SEQUOYAH - UNIT 2 3/4 7-1 Amendment No. 104, 187

TABLE 3.7-1 N

MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH j

INOPERABLE STEAM LINE SAFETY VALVES l

5 x

Maximum Allowable Power Range g

Maximus Number of Inoperable Safety Neutron Flux High Setpoint g

Valves on Any Doeratino Steam Generator (Percent of RATED THERMAL POWER) m 1

63 2

45 3

28 M.

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TABLE 3.7-2

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STEAM LINE SAFETY VALVES PER LOOP VALVE NUMBER LIFT SETTING fi 10

• N0ZZLE SIZE Loon 1 Loon 2 Loon 3 Loop 4 x

2-1-522 2-1-517 2-1-512 2-1-527 1064 psig 16 sq. in.

2-1-523 2-1-518 2-1-513 2-1-528 1077 psig 16 sq. in.

2-1-524 2-1-519 2-1-514 2-1-529 1090 psig 16 sq. in.

2-1-525 2-1-520 2-1-515 2-1-530 1103 psig 16 sq. in.

2-1-526 2-1-521 2-1-516 2-1-531 1117 psig 16 sq. in, w

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• The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating i

temperature and pressure.

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t SEQUOYAH - UNIT 2 3/4 7-4 AMEN 0 MENT NO.187

3/4.7 PLANT SYSTEMS BASES 3/4.7.1 TURBINE CYCLE 3/4.7.1.1 SAFETY VALVES The OPERABILITY of the main steam line code safety valves ensures that the secondary system pressure will be limited to within 110% (1194 psig) of the system design pressure during the most severe anticipated system operational transient. The maximum relieving capacity'is associated with a turbine trip from 100% RATED THERMAL POWER coincident with an assumed loss of condenser heat sink (i.e., no steam bypass to the condenser).

A In Mode 1 above 28% RTP, the number of MSSVs per steam generator required to be operable must be according to Table 3.7-1 in the accompanying LCO. At or below 28% RTP in Modes 1, 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 requirement for the MSSVs to be g operable in these modes.

The specified valve lift settings and relieving capacities are in accord-ance with the requirements of Section III of the ASME Boiler and Pressure Code, 1971 Edition. Thy total relieving capacity for all valves on all of the steam lines is 1.9 x 10 lbs/hr at 1170 9sig which is 127 percent of the total secondary steam flow of 1.493 x 10 lbs/hr at 100% RATED THERMAL POWER. A i

minimum of 2 OPERABLE safety valves per steam generator ensures that sufficient relieving capacity is available for the allowable THERMAL POWER restriction in Table 3.7-1.

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1 STARTUP and/or POWER OPERATION is allowable with safety valves inoperable within the limitations of the ACTION requirements on the basis of the reduction in secondary system steam flow and THERMAL POWER required by the reduced reac-tor trip settings of the Power Range Neutron Flux channels. The reactor trip setpoint reductions are derived on the following bases:

To calculate this setpoint, the governing equation is the relationship i

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 j

no subcooled feedwater). Thus, an algorithm for use in defining the revised Technical Specification table setpoint values would be:

Hi ( = (100/Q) where:

Hi ( - Safety Analysis power range high neutron flux setpoint, percent SEQUOYAH - UNIT 2 B 3/4 7-1 Amendment No.187

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PLANT SYSTEMS aASES 1

. Nominal NSSS power rating.of the' plant (including reactor-Q

=

coolant pump heat),'Mwt

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Conversion factor, 947.82 (Bt ec)

K:

Mi,nimum total steam flow rate capability of the operable MSSVs j

w,

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on any one steam generator:at the highest MSSV opening pressure including tolerance and accumulation, as appropriate, in 1b/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 o MSSVs ist the highest operable MSSV operating pressure,perable excluding j

the three highest capacity MSSVs.

heat of vaporization for steam at'the highest MSSV opening h

=

3 pressure including tolerance and accumulation, as appropriate, Stu/lba N

Number of loops in plant

=

The values calculated from this algorithm must then be adjusted lower to account for instrument and channel uncertainties.

3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM The OPERABILITY of the auxiliary feedwater system ensures that the Reactor Coolant System can be cooled down to less than 350*F from normal operating conditions in the-event of a total loss of off-site power.

The steam driven auxiliary feedwater pump is capable of delivering 880 gpa (total feedwater flow) and each of the electric driven auxiliary feedwater pumps are capable of delivering 440 gpa (total feedwater flow) to the entrance of the steam generators at steam generator pressures of 1100 psia. At 1100 psia the open steam generator safety valve (s) are capable of relieving at least 11% of nominal steam flow. A total feedwater flow of-440 gpa at pressures of 1100 psia is sufficient to ensure that adequate feedwater flow is.available to remove decay heat and reduce the Reactor Coolant System temperature to less than 350*F where the Residual Heat Removal System may be placed into~ operation.

The surveillance test values ensure that each pump will' provide at least 440 gpa plus pump recirculation flow against a steam generator pressure of 1100 psia.

l Each motor-driven auxiliary feedwater pump (one Train A and one Train B) supplies flow paths to two steam generators.

Each flow path contains an auto-matic air-operated level control valve (LCV). The LCVs have the same train designation as the associated pump and are provided trained air. The turbine-driven auxiliary feedwater pump supplies flow paths to all four steam genera-tors.

Each of these flow paths contains an automatic air-operated LCV, two of SEQUOYAH - UNIT 2 B 3/4 7-2 Amendment No. 105, 187

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l PLANT SYSTEMS BASES i

which are designated as Train A, receive A-train air, and provide flow to the same steam generators that are supplied by the B-train motor-driven auxiliary J

feedwater pump. The remaining two LCVs are designated as Train B, receive B-train air, and provide flow to the same steam generators that are supplied by the A-train motor-driven pump. This design provides the required redundancy to ensure that at least two steam generators receive the necessary flow assuming

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any single failure.

It can be seen from the description provided above that the loss of a single train of air (A or B) will not prevent the auxiliary feed-water system from ' performing its intended safety function and is no more severe i

than the loss of a single auxiliary feedwater pump. Therefore, the loss of a single train of auxiliary air only affects the capability of a single motor-driven auxiliary feedwater pump because the turbine-driven pump is still capable of providing flow to two steam generators that are separate from the other motor-driven pump.

Two redundant steam sources are required to be operable to ensure that at least one source is available for the steam-driven auxiliary feedwater (AFW) i pump operation following a feedwater or main steam line break. This require-i ment ensures that the plant remains within its design basis (i.e., AFW to two intact steam generators) given the event of a loss of the No. I steam generator because of a main steam line or feedwater line break and a single failure of the B-train motor driven AFW pump. The two redundant sources must be aligned such that No. I steam generator source is open and operable and the No. 4 steam generator source is closed and operable.

For instances where one train of emergency raw cooling water (ERCW) is l

declared inoperable in accordance with technical specifications, the AFW turbine-driven pump is considered operable since it is supplied by both trains of ERCW. Similarly, the AFW turbine-driven pump is considered operable when one train of the AFW loss of power start function is declared inoperable in accordance with technical specifications because both 6.9 kilovolt shutdown board logic trains supply this function. This position is consistent with American National Standards Institute /ANS 58.9 requirements (i.e., postulation of the failure of the opposite train is not required while relying on the TS limiting condition for operation).

3/4.7.1.3 CONDENSATE STORAGE TANK The OPERABILITY of the condensate storage tank with the minimum water volume ensures that sufficient water is available to maintain the RCS at HOT STAND 8Y conditions for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> with steam discharge to the atmosphere concur-rent with total loss of off-site power. The contained water volume limit includes an allowance for water not useable because of tank discharge line location or other physical characteristics.

SEQUOYAH - UNIT 2 B 3/4 7-2a Amendment No. 105, 174, 187

V

.o AMENDMENT NO. :.96 FOR SEQUOYAH UNIT NO.1 - DOCKET N0. 50-327 and

~ AMENDMENT NO. :.87 FOR SEQUOYAH UNIT NO. 2 - DOCKET NO. 50-328 DATED: April 4, 1995 DISTRIBUTION W/ ENCLOSURE Docket Files-

' PUBLIC SQN Reading File S. Varga 0-14-E-4 J. Zwolinski G. Hill T-5-C-3(2 per docket)

C. Grimes 0-II-E-22 ACRS(4)

OPA 0-2-G-5 0C/LFDCB T9-E10 E. Merschoff RII M. Lesser RII k

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ATTACHMENT TO LICENSE AMENDMENT NO. 196 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

Spillover page is provided to maintain document completeness.

REMOVE INSERT 3/4 7-1 3/4 7-1 3/4 7-2 3/4 7-2 3/4 7-3 3/4 7-3 3/4 7-4 3/4 7-4 B3/4 7-1 B3/4 7-1 83/4 7-2 B3/4 7-2 B3/4 7-2a B3/4 7-2a*

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.SEQUOYAH - UNIT 1 3/4 7-4 AMEN 0 MENT NO.196.

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3/4.7 PLANT SYSTEMS i

i BASES.

3/4.7.1 TURBINE CYCLE 3/4.7.1.1 SAFETY VALVES The OPERABILITY of the main steam line code safety valves ensures that l

the secondary system pressure will be limited to within 110% (1194 psig) of.

the system design pressure during the most severe anticipated system opera-tional transient. The maximum relieving capacity is associated with a turbine trip from 100% RATED THERMAL POWER coincident with an assumed loss of condenser heat sink (i.e...no steam bypass to the condenser).

In Mode 1 above 28% RTP, the number of MSSVs per steam generator required to be operable must be according to Table 3.7-1 in the accompanying LCO. At;or below 28% RTP in Modes 1, 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 requirement for the MSSVs to be operable in these modes.

j The specified valve lift settings and relieving capacities are in accor-dance with the requirements of Section III of the ASME Boiler and Pressure Code, 1971 Edition. Thy total relieving capacity for all valves on all of the steam lines is 1.9 x 10 lbs/hr at 1170 psig which is 127 percent of the total i

7 secondary steam flow of 1.493 x 10 lbs/hr at 100% RATED THERMAL POWER. A minimum of 2 OPERABLE safety valves per steam generator ensures that sufficient i

relieving capacity is available for the allowable THERMAL POWER restriction in j

Table 3.7-1.

l STARTUP and/or POWER OPERATION is allowable with safety valves inoperable within the limitations of the ACTION requirements on the basis of the reduction in secondary system steam flow and THERMAL POWER required by the reduced reac-tor trip settings of the Power Range Neutron Flux channels. The reactor trip setpoint reductions are derived on the following bases:

T9 calculate this setpoint, the governing equation is the relationship q = mih, where q is the heat input from the primary side, a is the steam flow rate and Ah is the heat of vaporization at the steam relief pressure (assuming no tubcooled feedwater). Thus, an algorithm for use in defining the revised i

Technical Specification table setpoint values would be:

1 Hi $ = (100/Q)

K where:

Hi ( = Safety Analysis power range high neutron flux setpoint, percent SEQUOYAH - UNIT 1 B 3/4 7-1 Amendment No. 196

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PLANT SYSTEMS BASES Nominal NSSS power rating of the plant (including reactor

.Q coolant pump. heat), Mwt Conversion factor, 947.82'fBtu/sec)

K Mwt wg Minimum total steam flow rate capability of the operable MSSVs' d

on any one steam generator at the highest MSSV opening pressure-including tolerance and accumulation, as appropriate,.in 1b/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.

h heat of vaporization for steam at the highest MSSV opening 3

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

The values calculated from this algorithm must then be adjusted lower to account for instrument and channel uncertainties.

3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM-The' OPERABILITY of the auxiliary feedwater system ensures that the Reactor Coolant System can be cooled down to less than 350*F from normal operating conditions in the event of a total loss of off-site power.

The. steam driven auxiliary feedwater pump is capable of delivering 880 gpa (total feedwater flow) and each of the electric driven auxiliary feedwater pumps are capable of delivering 440 gpa (total feedwater flow) to the entrance of the steam generators at steam generator pressures of 1100 psia.. At 1100

. psia the open steam generator safety valve (s) are capable of relieving at least 11% of nominal steam flow. A total feedwater flow of 440 gpa at pressures of 1100 psia is sufficient to ensure that adequate feedwater flow is available to remove decay heat and reduce the Reactor Coolant System temperature to less than 350*F where the Residual Heat Removal System may be placed into operation.

The surveillance test values ensure that each pump will provide at least 440 gpa plus pump recirculation flow against a steam generator. pressure of 1100 psia.

Each motcr-driven auxiliary feedwater pump (one Train A and one Train B) supplies flow paths to two steam generators. Each flow path contains an auto-

. matic air-operated level control valve (LCV). The LCVs have the same train designation as the associated pump and are provided trained air. The turbine-driven auxiliary feedwater pump supplies flow paths to all four steam genera-tors.

Each of these flow paths contains an automatic air-operated LCV, two of SEQUOYAH - UNIT 1 B 3/4 7-2 Amendment No. 115, 155,T96

PLANT SYSTEMS BASES which are designated as Train A, receive A-train air, and provide flow to the same steam generators that are supplied by the B-train motor-driven auxiliary feedwater pump. The remaining two LCVs are designated as Train B, receive B-train air, and provide flow to the same steam generators that are supplied by the A-train motor-driven pump.

This design provides the required redundancy to ensure that at least two steam generators receive the necessary flow assuming any single failure.

It can be seen from the description provided above that the loss of a single train of air (A or B) will not prevent the auxiliary feed-water system from performing its intended safety function and is no more severe

{

than the loss of a single auxiliary feedwater pump. Therefore, the loss of a i

single train of auxiliary air only affects the capability of a single motor-driven auxiliary feedwater pump because the turbine-driven pump is still capable of providing flow to two steam generators that are separate from the other motor-driven pump.

Two redundant steam sources are required to be operable to ensure that at least one source is available for the steam-driven auxiliary feedwater (AFW) pump operation following a feedwater or main steam line break. This require-ment ensures that the plant remains within its design basis (i.e., AFW to two intact steam generators) given the event of a loss of the No. I steam generator because of a main steam line or feedwater line break and a single failure of the B-train motor driven AFW pump. The two redundant sources must be aligned such that No. I steam generator source is open and operable and the No. 4 steam generator source is closed and operable.

For instances where one train of emergency raw cooling water (ERCW) is declared inoperable in accordance with technical specifications, the AFW turbine-driven pump is considered operable since it is supplied by both trains of ERCW. Similarly, the AFW turbine-driven pump is considered operable when one train of the AFW loss of power start function is declared inoperable in i

accordance with technical specifications because both 6.9 kilovolt shutdown board logic trains supply this function. This position is consistent with American National Standards Institute /ANS 58.9 requirements (i.e., postulation of the failure of the opposite train is not required while relying on the TS limiting condition for operation).

3/4.7.1.3 CONDENSATE STORAGE TANK The OPERABILITY of the condensate storage tank with the minimum water volume ensures that sufficient water is available to maintain the RCS at HOT STANDBY conditions for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> with steam discharge to the atmosphere concur-rent with total loss of off-site power. The contained water volume limit includes an allowance for water not useable because of tank discharge line location or other physical characteristics.

SEQUOYAH - UNIT 1 B 3/4 7-2a Amendment No. 115, 155, 196 l

/

3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.7.1.1 Main steam safety valves (MSSVs) shall be OPERABLE with lift settings as specified in Table 3.7-2.

APPLICABILITY: MODES 1, 2 and 3.*

ACTION:

a.

With one or more MSSVs inoperable, operation may proceed provided, that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable valve is restored to OPERABLE status or the Power Range Neutron Flux High Setpoint trip is reduced per Table 3.7-1.

The provisions of Specification 3.0.4 are not e,plicable.

b.

With the requirements of ACTION a., not met or with one or more steam generators with less than two MSSVs OPERABLE be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN in the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE RE0VIREMENTS 4.7.1.1 No additional Surveillance Requirements other than those required by Specification 4.0.5.

• With the reactor trip system breakers in the closed position.

l SEQUOYAH UNIT 1 3/4 7-1 Amendment No. 114, 196

.s TABLE 3.7-1 3

MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH INOPERABLE STEAM g

LINE SAFETY VALVES g

l-

x:

s Maximum Allowable Power Range g

Maximus Number of Inoperable Safety Neutron Flux High Setpoint-p Valves on Any Doeratina Steam Generator (Percent of RATED THERMAL POWER)

I 63 2

45 3

28 w

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STEAM LINE SAFETY VALVES PER LOOP 8jj VALVE NUMBER LIFT SETTING fi 1%)*

N0ZZLE SIZE Loon 1 Loon 2 Loon 3 Loon 4 z

1 1-1-522 1-1-517 1-1-512 1-1-527 1064 psig 16 sq. in.

1-1-523 1-1-518 1-1-513 1-1-528 1077 psig

' 16 sq. in.

1-1-524 1-1-519 l-1-514 1-1-529 1090 psig 16 sq. in.

1-1-525 1-1-520 1-1-515 1-1-530 1103 psig 16 sq. in.

1-1-526 1-1-521 1-1-516 1-1-531 1117 psig 16 sq. in, wis

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

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' WASHINGTON, D.C. 20086 4001 =

1 A,.....f TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT. UNIT 2

' AMENDMENT TO FACILITY OPERATING LICENSE 1

Amendment No.187 Y'

License No. DPR-79

{

1.

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

1 A.

The application for amendment by Tennessee Valley Authority (the a

licensee) dated December 16, 1994, and' supplemented February 10,

.)

1995, 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; j

B.

The facility will operate in conformity with the application, the~

provisions of the Act, and the rules-and regulations of the

~

Commission; l

C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and i

safety of the public, and (ii) that such activities will be-1 conducted in compliance with the Commission's regulations; i

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 l

'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.

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