ML20005B346

Amend 7 to License DPR-77,revising Tech Specs to Allow Deletion of Reactor Trip on Turbine Trip Below 50% Power Level

ML20005B346
Person / Time
Site:	Sequoyah
Issue date:	06/26/1981
From:	Adensam E Office of Nuclear Reactor Regulation
To:
Shared Package
ML20005B347	List: ML20005B346 ML20005B348 ML20005B349
References
NUDOCS 8107070516
Download: ML20005B346 (10)

Text

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i Ttuhr.SSLE YALLEY AUTn0RITY DOCKET NO. 50-327 SEQuGYAn HUCLEAR PLAhT, UWIT 1

/aEhbiitt4T TO FACILITY OPERATlhG LICEhSE Aaence nt No. 7 License ho. DPR-77 1.

Tne Nuclear Regulatory Conaission (the Conaission) havinj found that:

A.

Tne application for amenduent to tne Sequoyan Nuclear Plant, Unit 1 (the facility) facility Operating License ho. OPR-77 filed Dy the Tennessee Valley Autnority (licensee), dated hay 13 and 14,1961 complies with the standards and requirements of the Atoaic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set fortn in 10 CFa Chapter I; 8.

The facility will operate in conformity with the license, as aaended, the provisions of the Act, and the rules ano regulations of the Com-mission; C.

There is reasonable assuance (1) tnat the activities authorized by tnis amendment can be conducted without encangering the health and safety of the puolic, and (ii) that sucn activities will be conducteo in compliance with the Comission's regulations; D.

Tne issuance of tnis amencnent will not be Inimical to tne comon defense and security or to the nealth and safet;y of the public; and E.

The issuance of this amend.aent is in accorcance with 10 CFR Part 51 of the Conaission'., regulations and all applicable requirewnts. have been satisfied.

2.

Accorningly, the aanded license is herebj aiaended by page cnanges to the Appenoix A Technical Specifications as indicated in the attacumnts to this license amendment ano paragraph 2.C.(2) or FaciliI,/ Operating License 40.

DPR-077 is herebj a:;.cnded to read as follows:

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' (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 7, are hereby incorporated into the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This amended license is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY C0fflISSION

/9 Elinor G. Adensam, Acting Chief Licensing Branch #4 Division of Licensing

Attachment:

Appendix A Technical Specification Changes Date of Issuance: June 26, 1981 Y

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ATTACHMENT TO LICENSE MEkDf1ENT NO. 7 FACILITY OPERATil.G LICENSE NO. DPR-77 DOCKET NO. 50-327 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identifica by Arendment nuidser and contains vertical lines indicating the area of change. The corresponding overleaf pages are also provided to inaintain docueent corapleteness.

Overleaf A.nended Page Page 2-8 2-7 3/4 3-3 B2-7 3/4 3-8 3/4 3-4 3/4 3-7 OFFICE k

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TABLE 2.2-1 (Continued) en m

jj REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS x

i FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES C

'i 21.

Turbine Impulse Chamber Pressure -

< 10% Turbine Impulse

< 11% Turbine Impulse (P-13) Input to Low Power Reactor Trips Pressure Equivalent Pressure Equivalent Block P-7 22.

Power Range Neutron Flux - (P-8) Low

< 35% of RATED

< 36% of RATED Reactor Coolant foop Flow, and Reactor THERMAL POWER THERMAL POWER Coolant Pump Breaker Position 23.

Power Range Neutron Flux - (P-10) -

2 10% of RATED 1 9% of RATED Enable block of Source, Intermediate, THERMAL POWER THERMAL POWER and Power Range (low setpoint) reactor i

Trips 4

}'

24.

Reactor Trip P-4 Not Applicable Not Applicable 25.

Power Range Neutron Flux - (P-9) -

5 50% of RATED

$ 51% of RATED Blocks Reactor Trip for Turbine THERMAL POWER THERMAL POWER Trip Below 50% Rated Power NOTATION I

+

b I

NOTE 1:

Overtemperature AT (

) 5 AT, {K) - K2 (1 + T 8 2 )[T(

)-T'] + K ( - )~

1(O )}

3 1 + I)S 3

4 I*Tb N

f

= Lag compensator on measured AT l[

where:

j 1

8 I

o

[

t

= Time constants utilized in the lag compensator for AT T = 2 secs.

j 31 o

[,

AT

= Indicated AT at RATED THERMAL PGWER g

K

$ 1.14 j

K

= 0.009 2

TABLE 2.2-1 (Continued) h REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS O

j NOTATION (Continued)

NOTE 1:

(Continued) zZ 1+1b2 The function gererated by the lead-lag controller for T,yg dynamic compensation w

=

l*T53 2' & '3 Time constants utilized in the lead-lag controller for T,yg, t2 = 33 secs.,

T

=

3 = 4 secs.

1 T

Average temperature "F

=

1 Lag compensator on measured T

=

1+I5 avg 4

Time constant utilized in the measured T,yg lag compensator,1 = 2 secs.

1

=

4 4

4 T'

< 578.2"F (Nominal T at RATED THERMAL POWER) avg K

0.00043

=

3 P

Pressurizer pressure, psig

=

P' 2235 psig (Nominal RCS operating pressure)

=

Laplace transform operator (sec-l)

S

=

and f (61) is a function of the indicated difference between top and bottom detectors 3

J of the power-range nuclear ion chambers; with gains to be selected based on measured instrument response during plant startup tests such that:

(i) for q q between - 30 percent and + 4 percent f and q arephrcenkRATEDTHERMALPOWERinthetopandbotlo(al)=0(whereqborereNpectively, I

m halves of the is total THERMAL POWER in percent of RATED THERMAL POWER).

and qt + 9b

.m

l SAFETY LIMITS BASES Turbine Trip A Turbine Trip causes a direct reactor trip when operating above P-7.

Each of the turbine trips provide turbine protection and reduce the severity of the ensuing transient.

No credit was taken in the accident analyses for opera-tion of these trips.

Their functional capability at the specified trip settings I

is required to enhance the overall reliability of the Reactor Protection System.

t i

Safety Injection Input from ESF If a reactor trip has not already been generated by the reactor protective instrumentation, the ESF automatic actuation logic channels will initiate a reactor trip upon any signal which initiates a safety injection. This trip is provided to protect the core in the event of a LOCA.

The ESF instrumentation channels which initiate a safety injection signal are shown in Table 3.3-3.

Reactor Trip System Interlocks The Reactor Trip System Interlocks perform the following functions on increasing power:

P-6 Enables the manual block of the source range reactor trip (i.e.,

prevents premature block of source range trip).

P-7 Defeats the automatic block of reactor trip on:

Low flow in more P-13 than one primary coolant loop, reactor coolant pump undervoltage and underfrequency, pressurizer low pressure, and pressurizer high level.

P-8 Defeats the automatic block of reactor trip on low RCS coolant flow l

in a single loop.

P-9 Defeats the automatic block of Reactor Trip on Turbine Trip.

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P-10 Enables the manual block of reactor trip on power range (low setpoint),

intermediate range, as a backup block for source range, and intermediate range rod stops (i.e., prevents premature block of the noted functions).

On decreasing power, the opposite function is performed at reset setpoints.

P-4 Reactor tripped - Actuates turbine trip, closes main feedwater valves on T below setpoint, prevents the opening of the main feedwater valv$l9which were closed by a safety injection or high steam generator water level signal, allows manual block of the automatic reactuation of safety injection.

Reactor not tripped - defeats manual block preventing automatic reactuation of safety injection.

SEQUOYAH - UNIT 1 B 2-7 Amendment No. 7

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TABLE 3.3-1 (Continued) r'n" EE REACTOR TRIP SYSTEM INSTRUMENTATION S

"x MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPEP.ABLE MODES ACTION c:

12.

Loss of Flow - Single Loop 3/ loop 2/ loop in 2/ loop in 1

7

~~

fahove P-8) any oper-each oper-ating loop ating loop 13.

Loss of Flow - Two Loops 3/ loop 2/ loop in 2/ loop 1

7 (Above P-7 and below P-8).

two oper-each oper-ating loops ating loop 14.

Main Steam Generator 3/ loop 2/ loop in 2/ loop in 1, 2 7

la Water Level--Low-Low any oper-each oper-ating loop ating loop e.

Es 15.

Steam /Feedwater Flow 2/ loop-level 1/ loop-level 1/ loop-1, 2 7

1 w

Mismatch and Low Steam and coincident level and Generator Water Level 2/ loop-flow with 2/ loop-flow mismatch in 1/ loop-flow mismatch or same loop mismatch in 2/ loop-level same loop and 1/ loop-flow mismatch 4-1/ bus 2

3 1

6, 16.

Undervoltage-Reactor Coolant Pumps 17.

Underfrequency-Reactor Coolant' 6,

4-1/ bus 2

3 1

Pumps g

l

18. Turbine Trip A.

Low Fluid Oil Pressure 3

2 2

1 7

B.

Turbine Stop Valve Closure 4

4 4

1 13 i

1 I

1

TABLE 3.3-1 (Continued) v, m

{l REACTOR TRIP SYSTEM INSTRUMENTATION

_c E

i MINIMUM EI TOTAL NO.

CHANNELS CHANNELS APPLICABLE Ej FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION i

19.

Safety Injection Input from ESF 2

1 2

1, 2 1

l 20.

Reactor Trip Breakers 2

1 2

1, 2, and

• 1 21.

Automatic Trip Logic 2

1 2

1, 2, and

• 1 22.

Reactor Trip System Interlocks A.

Intermediate Range l

Neutron Flux P-6 2

1 2

2, and*

8a Ad B.

Power Range Neutron Flux - P-7 4

2 3

1 8b Y

C.

Turbine Impulse Chamber 4

i Pressure - P-13 2

1 2

1 8b D.

Power Range Neutron 4

Flux - P-8 4

2 3

1 8c I

E.

Power Range Neutron Flux - P-10 4

2 3

1, 2 8d

]

F.

Power Range Neutron 4

2 3

1 8e Flux - P-9 G.

Reactor Trip - P-4 2

1 2

1, 2, and* 14 i

g.

e it 2

n EF L

4 i

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INSTRUMENTATION TABLE 3.3-1 (Continued)

ACTION 8 -

With less than the Minimum Number of Channels OPERABI declare the interlock and all affected channels of the funct s listed below inoperable and apply the appropriate ACTION statement (s).

Functions to be evaluated are:

a.

Source Range Reactor Trip.

b.

Reactor Trip Low Reactor Coolant Loop Flow (2 loops)

Undervoltage Underfrequency Pressurizer Low Pressure Pressurizer High Level c.

Reactor Trip Low Reactor Coolant Loop Flow (1 loop) d.

Reactor Trip Intermediate Rarige Low Power Range Source Range e.

Reactor Trip Turbine Trip ACTION 9 -

With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in 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 />; however, one channel associated with an operating loop may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.1.1.1.

ACTION 10 -

With one channel inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or. educe THERMAL POWER to below the P-8 (Block Low Reactor Coolant Pump Flow) setpoint breaker within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Operatio.. below the P-8 (Block of Low Reactor Coolant Pump Flow) setpoint breaker may continee pursuant to ACTION 11.

ACTION 11 -

With less thLn the Minimum Number of Channels OPERABLE, operation may continue provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

ACTION 12 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel ta OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or 'e in HOT STANDBY o

within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and/or open the reactor trip breakers.

SEQUOYAH - UNIT 1 3/4 3-/

Amendment. No. 7

' INSTRUMENTATION TABLE 3.3-1 (Continued)

ACTION 13 -

With the r.v.nber of OPERABLE channels one less than the Total Number ot Channels and with the THERMAL POWER level aoove the P-7 (Block of Low Power 9eactor Trips) setpoint, place the inoperable channel in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, operation may continue until performance of the next required CHANNEL FUNCTIONAL TEST.

ACTION 14 -

With the number of channels CPERABLE one les: than required by the Minimum Channels OPERA 9LE requirement, ba in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

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SEQUOYAH - UNIT 1 3/4 3-8 y

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