ML20246F773

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Amends 120 & 109 to Licenses DPR-77 & DPR-79,respectively, Revising Tech Specs Re Containment Sys to Delete Surveillance Requirements on Each Containment Purge Isolation Valve & Adding Requirement on Each Purge Valve
ML20246F773
Person / Time
Site: Sequoyah  
Issue date: 07/05/1989
From: Black S
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20246F777 List:
References
NUDOCS 8907140029
Download: ML20246F773 (12)


Text

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\\.~... j'",E wash NGTON, D. C,20555 TENNESSEEVALLEYAUTHORIM DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.120 License No. DPR-77 1.

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

A.

The application for a;nendment by Tennessee Valley Authority (the licensee) dated December 5, 1988, 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 (1) 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.

8907140029 890703 PDR ADOCK 05000327 P

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  • 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. OPR-77 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B,.as revised through Amendment No.120, 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.

FOR THE NUCLEAR REGULATORY COMMISSION b

Suzanne B ack, Assistant Director for Projects TVA Projects Division Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: July 5, 1989 1

______.___-m

~ ATTACHMENT TO LICENSE AMENDMENT NO. 120

['

FACILITY CPERATING LICENSE NO. OPR-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. Overleaf pages* are provided to

. maintain document completeness.

REMOVE INSERT 3/4 6-15 3/4 6-15 3/4 6-16 3/4 6-16*

3/4 6-18 3/4 6-18 1

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CONTAINMENT SYSTEMS CONTAINMENT VENTILATION SYSTEM l:

LIMITING CONDITION FOR OPERATION

3. 6.1. 9 One pair (one purge supply line and one purge exhaust line) of containment purge system lines may be open; the containment purge supply and exhaust isolation valves in all other containment purge lines shall be closed.

' Operation with purge supply or exhaust isolation valves open for either purging or venting shall be limited to less than or equal to 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> per 365 days.

The 365 day cumulative time period will begin every April 15.

[

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

With a purge supply or exhaust isolation valve open in excess of the a.

above cumulative limit, or with more than one pair of containment purge system lines open, close the isolation valve (s) in the purge j

(

line(s) within one hour or 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

b.

With a containment purge supply and/or exhaust isolation valve having a measured leakage rate in excess of 0.05 L, restore the a

inoperable valve to OPERABLE status within 24. hours, otherwise be in l

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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURF 'LLANCE REQUIREMENTS 4.6.1.9.1 The position of the containment purge supply and exhaust isolation valves shall be determined at least once per 31 days.

4.6.1.9.2 The cumulative time that the purge supply and exhaust isolation valves are open over a 365 day period shall be determined at least once per 7 days.

4.6.1.9.3 At least once per 3 months, each containment purge supply and exhaust isolation valve shall be demonstrated OPERABLE by verifying that the measured leakage rate is less than or equal to 0.05 L, and by verifying that when the measured leakage rate is added to the leakage rates determined pursuant to Specification 4.6.1.2.d for all other type B and C penetrations, the combined leakage rate is less than or equal to 0.60 L,.

SEQUOYAH - UNIT 1 3/4 6-15 Amendment No. 18, 120 L

CONTAINMENT SYSTEMS 3/4.'6.2 DEPRESSURIZATION AND COOLING SYSTEMS

~ CONTAINMENT SPRAY SYSTEM

. LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent trains of both the containment spray and residual heat removal spray shall be OPERABLE with each train comprised of:

a.

A Containment Spray train with:

1.

One OPF8AELE Containment Spray pump.

2.

One ORU3BLE Containment Spray heat exchanger.

3.

An OPERABLE flow path capable of taking suction from the refueling water storage tank and transferring suction to the containment sump, and b.

A RHR Spray train with:

1.

One OPERABLE residual heat removal pump, 2.

One OPERABLE residual heat removal heat exchanger, and 3.

An 00FRABLE flow path capable of taking suction from the con-tairceit sump.

APPLICABILITY:

MODES 1, 2, 3 and 4.*

ACTION:

With one' train of containment spray or residual heat removal spray inopecable, restore the inoperable spray train to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 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 />; restore the inoperable sr y train to OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS I

4.6.2.1.1 Each Containment Spray train shall be demonstrated OPERABLE:

At least once per 31 days by verifying that each valve (manual, a.

power' operated or automatic) in the flow path that is not locked, i

sealed, or otherwise secured in position, is in its correct position.

l

  • 0PERABILITY of RHR Spray trains is not required in MODE 4.

SEQUOYAH - UNIT 1 3/4 6-16 Amendment fto. 12., 69

-- - __ L

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c CONTAINMENT SYSTEMS l SURVEILLANCE REQUIREMENTS (Continued) 4.6.3.2. Each, isolation valve specified in Table 3.6-2 shall b'e. demonstrated-

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OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months-by:

Verifying that on a Phase A containment' isolation. test ' signal,. each'-

a.

Phase A isolation valve actuates to its isolation position.

b.

Verifying that on a Phase'B containment isniation test signal, each-Phase B isolation valve actuates to its isolati;n. position.-

Verifying'that on a Containment Ventilation isolation test signal,.

c.

each Containment Ventilation Isolation valve actuates to-its isolation position.

d.

Verifying that on a high containment pressure isolation test-signal, each Containment Vacuum Relief Valve actuates to its. isolation position.

Verifying that on a Safety Injection test signal that the Normal o

e.

Charging Isolation valve actuates to its isolation position.

-4.6.3.3.The isolation time of each power operated or automatic valve of.

Table 3.6-2fshall be determined to be within its limit when tested pursuant to Spt.Ification 4.0.5.

SEQUOYAH - UNIT 1 3/4 6-18 Amendment No. 12, 81., 101, 120

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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT, UNIT 2 A_MENDMENT TO FACILITY OPERATING LICENSE Amendment No. 109 Licensa No. DPR-79 1.

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

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated December 5, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Comission's rules and regulations set forth in 10 CFR Chapter'I; 8.

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

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

There is reasonable assurance (1) that the activities authorized by this ainendment can be conducted without endangering the health and safety of the public, and (ii)-that such activities will be conducted in complidnce with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon 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.

1

l 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 amended to read as follows:

.(2) Technical Specifications l

The Technicdl Specifications contained in Appendices A and B, as l

revised through Amendment No.109, are hereby incorporated in the I

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.

l FOR THE NUCLEAR REGULATORY COMMISSION b

Suzann lack, Assistant Director for Projects TVA Projects Division Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical l.

Specifications l

Date of Issua~nce: July 5, 1989 l

l L

4 lh ATTACHMENT TO LICENSE AMENDMENT NO. 109

.p i

FACILITY OPERATING LICENSE N0. DPR-79 DOCKET NO. 50-328 j"

b Revise the Appendix A Technical Specificat'ons by removing the pages l-identified below and inserting the enclosea pages. _ -The revised pages j

dre identified by the' captioned amendment number and Contain marginal lines indicating the area of change.

Overleaf pages* are provided to maintain document completeness..

i 1

REMOVE INSERT F

3/4 6-15 3/4 6-15 3/4 6-16 3/4 6-16*

L 3/4 6-18 3/4 6-18 i

1 Al

h e

. ~i CONTAINMENT SYSTEMS

. y CONTAINMENT VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.9~ One pair (one purge supply line and one purge exhaust line) of containment purge system lines may be open; the containment purge supply and exhaust isolation valves in all other containment purge lines shall be closed.

Operation with purge supply or exhaust isolation valves open for either purging or venting shall be limited to.less than or equal to 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> per 365 days.

The 365' day cumulative time period will begin every January 1.

1 l

APPLICABILITY:

MODES 1, 2, 3, and 4.

L ACTION:

With a purge supply or exhaust isolation valve open in excess.of the l

a.

above cumulative li! nit, or with more than one pair of containment purge system lines open, close the isolation valve (s) in the purge line(s) within one hour or be in at least HOT STANDBY within the next l

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, b.

With a containment purge supply and/or exhaust isolation valve having a measured leakage rate in excess of 0.05 L,, restore the inoperable valve to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, otherwise 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4 6.1.9.1 The position of the containment purge supply and exhaust isolation valves shall be determined at least once per 31 days.

4.6.1.9.2 The cumulative time that the purge supply aad exhaust isolation valves are open over a 365 day period shall be determined at least once per 7 days.

4.6.1.9.3 At least once per 3 months, each containment purge supply and exhaust isolation valve shall be demonstrated OPERABLE by verifying that the measured leakage rate is less than or equal to 0.05 L, and by verifying that when the measured leakage rate is added to the leakage rates determined pursuant to Specification 4.6.1.2.d for all other type B and C penetrations, the combined leakage rate is less than or equal to 0.60 L

  • a I

SEQUOYAH - UNIT 2 3/4 6-15 Amendment No. 9,109

_JL

Bt CONTAINMENT SYSTEMS

1..

1, 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS j.

CONTAINMENT SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent trains of both the containment spray and residual heat I

removal spray shall be OPERABLE with each train comprised of:

l a.

A Containment Spray train with:

1.

One OPERABLE Containment Spray pump.

2.

One OPERABLE Containment Spray heat exchanger.

3.

An OPERABLE flow path capable of taking suction from the refueling water storage tank and transferring suction to the containment sump, and b.

A RHR Spray train with:

1.

One OPERABLE residual heat removal pump.

2.

One OPERABLE residual heat removal heat exchanger, and 3.

An OPERABLE flow path capable of taking suction from the con-tainment sump.

APPLICABILITY:

MODES 1, 2, 3 and 4.*

ACTION:

With one train of containment spray or residual heat removal spray inoperable, restore the inoperable spray train to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Jr 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 />, restore the inoperable spray train to OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.'6.2.1.1 Each Containment Spray train shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked sealed, or otherwise secured in position, is in its correct position.

  • 0PERABILITY of RHR Spray trains is not required in MODE 4.

SEQUOYAH - UNIT 2 3/4 6-16 Amendment No. 61 aJ

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V CONTAINMENT SYSTEM 5 4

SURVEILLANCE REQUIREMENTS (Continued)-

'4.6.3.2 Each. isolation valve specified in Table 3.6-2 shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at-least once per 18 months by:

. Verifying that on a Phase A containnient isolation test-signal, each a.

Phase A isolation valve actuates to its isolation position.

b.

Verifying that'on a Phase B containment iso'ation test signal, each Phase B isolation valve actuates to'its isolation position.-

Verifying that on a. Containment Vent'lation isolation' test signal, c..

each Containment Ventilai.i n Isolation valve actuates to its.

1 solation position.

d.

Verifying that on a high containment pressure isolation test signal, each Containment Vacuum Relief Valve' actuates to its isolation position.

Verifying that on a Safety Injection test signal that the Normal-e.

Charging Isolation valve actuates to its isolation position.

4.6.3.3 The isolation time of each power operated or automatic' valve of Table 3.6-2 shall be determined to be within its limit when tested pursuant to Specification.4.0.5.

SEQUOYAH - UNIT 2 3/4 6-18 Amendment No. 72, 90, 104, 109 fl