Text

Amends 160 & 150 to Licenses DPR-77 & DPR-79,respectively, Revising Actions Required When 6.9 Kv Shutdown Board Engineered Safety Feature Actuation Sys & EDG LOP Instrumentation Inoperable
	ML20099C683
Person / Time
Site:	Sequoyah
Issue date:	07/24/1992
From:	Hebdon F; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20099C687	List: ML20099C683; ML20099C698;
References
	NUDOCS 9208040223
	Download: ML20099C683 (12)
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UNITED STATES E

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%,.... + f TENNESSEE VALLEY AUTHOR 111 QQGET NO. 50-327 SEQUOYAH NUCLEAR PLANT. UNIT 1 MEJJpjfNT TO FACILITY OPERATlHG LICENSE Amendment No.160 License No. DPR-77 1.

The N d ear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated November 27, 1991, 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.

Th..acility 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 ne cunducted in corpliance 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.

9208040223 920724 PDR ADOCK 05000327 P

PDR

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 */7 is hereby amended to read as follows:

(2) lechnical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.160, 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 30 days.

1 FOR THE NUCLEAR REGULATORY COMMISSION i

/~

Frederick J. Hebdon, Director Project Directorate 11-4 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: July 24,1992

ATTACHMENT TO llCENSE AMENDMENT NO.160 FAtlllTY OPCRATING 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.

REMOVE INSERT 3/4 3-21 3/4 3-21 3/4 3-23 3/4 3-23 3/4 3-23a 3/4 3-23a

+

____ __ _ __ m

[

I TABLE 3.3-3 (Continued) y, 58 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION Yc MINIMUM i

j TOTAL NO.

CHANNELS CHANNELS APPLICABLE g

FUNCTIONAL UNIT OF CHANNELS TO TRIP GPERABLE MODES ACTION j

Z

7. LOSS OF POWER j

y 6

i a.

6.9 kv Shutdown Board I

--Loss of Voltage l

1.

Start Diesel 2/ shutdown 1 loss of 2/ shutdown 1, 2, 3, 4 35*

l f

i Generators board voltage on board any shutdown

[

-j' board l

t 2.

Load Shedding 2/ shutdown 1/ shutdown 2/ shutdown 1, 2, 3, 4 34*

l q

board board board b.

6.9 kv Shutdown Board

[

Degraded Voltage 1.

Voltage Sensors 3/ shutdown 2/ shutdown 2/ shutdown 1, 2, 3, 4 34 l

l board board board i

j 2.

Diesel Generator 2/ shutdown 1/ shutdown 1/ shutdown 1,

2,. 3, 4 34 l

Start and Load board board board Shedding Timer y

i

=

3.

SI/ Degraded 2/ shutdown 1/ shutdown 1/ shutdown 1, 2, 3, 4 34 i

E Voltage Enable board board board 5

Timer i

i 8.

ENGINEERED SAFETY FEATURE l

i y

ACTUATION SYSTEM INTERLOCKS

[

i

$a a.

Pressurizer Pressure -

3 2

2 1,2,3 22a P-11/Not P-11

'y b.

Deleted q

c.

Steam Generator 3/ loop 2/ loop 3/ loop 1, 2 22c

[e level P-14 any icop i

I t

?

y.-

TABLE 3.3-3 (Continued) l ACTION 21 -

With less than the Minimum Number of Channels OPERABLE, declare the associated auxiliary feedwater pump inoperable, j

and comply with the ACTION requiremente of Specification 3.7.1.2.

ACTION 22 With less than the Minimum Number of Channels OPERABLE, declare i

the interlock inoperable and verify that all affected channels of the functions listed below are OPERABLE or apply the I

appropriate ACTION stateraent(s) for those functions.

Functions to be e M uated are a.

Safety Injection l

Pressurizer Pressure

}

Steam Line Pressure Negative Steam Line Pressure Rate b.

Deleted c.

Turbine Trip Steam Generator Level High-High Feedwater Isolation Steam Generator Level High-High i

l ACTION 23 -

With the number of OPERABLE channels one less than the Total l

Number of Channels, 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 at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1.1.

ACT:CN 24 -

With the number of OPERABLE channels one less than the Total Number of Channels, 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 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 at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 25 -

With tha number of OPERABLE channels one less than the Total Number of Channels, 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 declare the associated valve inoperable and take the ACTION required by Specification 3.7.1.S.

ACTION 34 -

a.

With the number of OPERABLE channels one less than the lotal Number of Channels, restore the inoperaole channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 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 COLD SHUT-DOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With the number of OPERABLE channels less than the Total Number of Channels by more than one, declare the associated 6,900-volt shutdown board inoperable, and comply with the action requirements of Specification 3.8.2.1 or 3.8.2.2 as applicable.

SEQUOYAH - UNIT 1 3/4 3-23 Amendment No. 12, 63, 129, 141 160

e s

I TABLE 3.3-3 (Continued)

ACTION 35 -

With t.he number of OPERABLE channels less than the Total Number of Channels by one or more, declare the associated diesel generator set inoperable, and comply with the action requirements of Specification 3.8.1.1 or 3.8.1.2 as applicable.

ACTION 36 -

With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may 3

proceed provided the following conditions are satisfied:

l a.

The inoperable channel is placed in the tripped cond; tion within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

For the affected protection set, the Trip Time Delay for one affected steam generator (T ) is adjusted to 3

match the Trip Time Delay for trultiple affected steam generators (T ) within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

M c.

The Minimum Channels OPERABLE requirement is met; however, I

the inoperable channel may be bypassed for up te 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testi!.g of otner channels per Speci-fication 4.3.2.1.1.

ACTION 37 -

With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided that within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , for the affected protection set, the Trip Time Delays (T and T ) threshold 3

g power level for zero secondstimedelayisadjustedto0%RTP.

ACTION 38 -

With the number of OPERABLE channels one less than the Total Number.of Channels, STARTUP and/or POWER OPERATION may proceed provided that within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , for the affected protectiun set, the Steam Generator Water Level - Low-Low (EAM) channels trip setpoint is adjusted to the same value as 5 team Generator Water Level - Low-Low (Adverse).

SEQUOYAH - UNIT 1 3/4 3-23a Amendment No. 141, 160

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UNITED STATES n

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NUCLEAR REGULATORY COMMISSION WASHINoToN. D C. 20f66 o.

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TENNESSEE VALLEY AltIjiqPJIX DOCKET NO. 50-328 1[0U0fAH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING llCENSE Amendment No.150 License No. DPR-79 4

1.

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

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated November 27, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Commission's rules and regulttions set forth in 10 CFR Chapter I;

~

B.

The facility will operate in conformity with the application, th9 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 safe +.y 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 applicabla requirements have been satisfied.

+

^

l t

3 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-79 is hereby 4

amended to read as follows:

(2) lechnical Specifications i

The Technical Specifications contained in Appendices A and B, as J

revised through Amendment No.150, 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 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION i

"f r

Frederick J. Hebdon, Director ProjPCt Directorate-4 Division of Reactor Projects - I/11 Office of Nuclear Reactor Regulation i

Attachment:

j Changes to the Technical i Specifications Date of Issuance: July 24, 1992 l 1 t e 3 ~

i i i ATTACHMENT TO LIC1 HSE AMENDMENT NO.iSC i FACIllTY OPERATING LICENSE NO. OPR-79 DOCKET NO. 50-328 i I Revise the Appendix A Technical Specifications W removing the pages identified below and insertf'g the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of chlage. l REMOVE INSERT 3/4 3-21 3/4 3-21 1 3/4 3-23 3/4 3-23 1 3/4 3-23a 3/4 3-23a .1 1 S ,vr-w., ,w... .#.y.~,.~..cy,,, r, +o,-

l S t ( g TABLE 3.3-3 (Contineed) x3 E ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION i g MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE i ' E FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES

CTION

-e m

7. LOSS UF POWER t

I a. 6.9 kv Shutdown Board i --Loss of Voltage l f i 1. Start Diesel 2/.J.utdown 1 loss of 2/ shutdown 1, 2, 3, 4 35* Generators board voltate on board any shutdown board R 2. Load Shedding 2/ shutdown 1/ shutdown 2/ shutdown 1, 2, 3, 4 34* board board board T U b. 6.9 kv Shutdewn Board Degraded Voltage 1. Voltage: Sensors 3/ shutdown 2/shutdosm 2/ shutdown 1, 2, 3, 4 34 l Doard board board i I l [ 2. Diesel Generator 2/ shutdown 1/ shutdown 1/shutdewn 1, 2, 3, 4 34 Start and Load board board board [ Shedding Timer 5 n l i R 3. SI/ Degraded 2/ shutdown 1/ shutdown 1/ shutdown 1, 2, 3, 4 34 2 Vcitage Enable board board board ] 5 Timer 5 = ( e ( o

TABLE 3.3-3(Continued} ACTION 21 - With less than the Minimum Number of Channels OPERABLE, declare the associated auxiliary feedwater pump inoperable, and comply with the ACTION requirements of Specification 3.7.1.2. ACTION 22 With less than the Minimum Humber of Channels OPERABLE, de-clare the interlock inoperable and serify that all affected channels of the functions listed below are OPERABLE or apply the appropriate ACTION statement (s) for those functions. Functions to be evaluated are: a. SafetyInjection Pressurizer Pressure Steam Line Pressure Nega*4ve Steam Line Pressure Rate b. Deleted c. Turbine Trip Steam Generator Level High-High Feedwater Isolation Steam Generator Level High-High ACTION 23 - With the number of OPERABLE channels one less than the Total Number of Channels, be in at least HOT STANDBY within 6 hours and in at least HOT SHUT 00WN within the following 6 hours; however, one channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.2.1.1. ACTION 24 - With the number of OPERAB E channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLL status within 48 hours or be in at least HOT STANDBY within 6 hours and in at least HOT SHUT 00WN within the following 6 hours. ACTION 25 - With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPEFABLE status within 48 hours or declare the associated valve inoperable and take the ACTION required by Specification 3.7.1.5. ACTION 34 - a. With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUT 00WN within the following 30 hourt. b. With the number of OPERABLE channels less than tra Total Number of Channels by more than one, declare the associated 6,900-volt shutdown board inoperable, and comply with the acti;n requirements of Specification 3.8.2.1 or 3.8.2.2 as applicable. SEQUOYAH - UNIT 2 3/4 3-23 Amendment No. 55, 116, 132, 150

i EBLE3.3-3(Continue,d_} i i ACTION 35 - With the number of OPERABLE channels less than the Total l Number of Channels by one or more, declare the associated 1 diesel generator set inoperable, and comply with the j action requirements of Specification 3.8.1.1 or 3.8.1.2 as applicable. ] j ACTION 36 - With the number of OPERABLE channels one less than the Total Number of Channels, 51 ARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied: a. The inoperable channel is placed in the tripped condition witnin 6 hours. b. For the affected protection set, the Trip Time Delay for one affected steam generator (T ) is adjusted to 3 match the Trip) lime Delay for multiple affected steam 2 generators (T within 4 hours. g c. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours for surveillance testing of other channels per Specification 4.3.1.1.1. ACTION 37 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or i'i'R OPERATION may proceed provided that within 6 hours, for the affected protection set, the Trip Time Delays (1 and T ) threshold 3 M power level for zero seconds time delay is adjusted to 0% RTP. ACTION K - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided that within 6 hours, for the affected pro-tection set, the Steam Generator Water Level - Low-Low (EAM) channels trip setpoint is adjusted to the same value as Steam Generator Water Level - Low-Low (Adverse). SEQUOYAH - UNIT 2 3/4 3-23a Amendment No. 132, 150 -}}

ML20099C683

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