ML20236D178

Amends 60 & 52 to Licenses DPR-77 & DPR-79,respectively, Increasing Setpoint of Radiation Monitors in Spent Fuel Area & Clarifying Enrichment Limits of Fuel Stored in Spent Fuel Pool & New Fuel Storage Areas

ML20236D178
Person / Time
Site:	Sequoyah
Issue date:	10/19/1987
From:	Zwolinski J NRC OFFICE OF SPECIAL PROJECTS
To:
Shared Package
ML20236D182	List: ML20236D178 ML20236D194
References
NUDOCS 8710280057
Download: ML20236D178 (14)

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'TENNESSFE VA,LLEY AUTHORITY-DOCKET NO. 50-327.

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SEQUOYAH NUCLEAR PLANT,! UNIT 1-AMENDMENT TO FACILITY OPERATING LICENSE-1 Amendment No. 60 License-. No.-. DPR-77 1.

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

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A.-

The' application for amendment by Tennessee. Valley Authority (the -

licensee) dated October 22, 1985, complies with'the standards and requirements ofithe Atomic-Energy Act of:1954.'as amended-(the Act),

and the Comission's rules and regulations set forth' in 10 CFR i

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 '

Comission;;

C.

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

- safety of the public, and (ii) that such activities will be conducted in compliance 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 Comission's regulations and all applicable requirements have been satisfied.

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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. DPR-77 is hereby amended to read as follows:

(2) Technical Specifications 1

The Technical Specifications contained in Appendices A and B, as revised through Amendment. No. 60, are hereby incorporated in the license. The licensee shall operate the facility in accordance with l

the Technica1' Specifications.

3.

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

NU{LEARREGULAplRYhMMISSION FOR TH i

8-X 1

John A, Zwolinski, Assistant Director for )rojects TVA Projects Division

.l Office of Special Projects

Attachment:

Changes to the Technical' Specifications l

Date of Issuance: October 19, 1987 l

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' ATTACHMENT T0 LICENSE AMENDMENT NO. 60-

-r FACILITY-0PERATING LICENSE NO. DPR-77 DOCKET NO. 50-327-

' Revise 'the. Appendix A Technical Specifications by removing;the pages j

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 l

j naintain document completeness.

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INSERT REMOVE i

3/4 3-39 3/4 3-39*

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3/4 3-40 3/4 3-40.

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-1 INSTRUMENTAL::N 3/4.3.3 MONITORING INSTRUMENTATION-RA0!ATION MONITORING INSTPUHENTATION

.q LIMITING CONDITION FOR OPERATION in Taele 3.3.3.1 The radial.iun mGr.itoring instrumentation channels shown 3.3-6 shall ce OPERABLE with their alarm / trip setpoints within the soecified.

limits.

APPLICABILITY:

As shown in Table 3.3-6.

ACTION:

With a radiation monitoring channel alarm / trip setpoint exceeding the value shown in Table 3.3-6, adjust the setpoint to within ne a.

limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel inoperable, With one or more radiation monitoring channels inoperable, take tr.e b.

ACTION shown in Table 3.3-6.

The provisions of Specifications 3.0.3 and 3.0.4 are not c.

applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.1 Each radiatici) monitoring instrumentation channel shall be demons *.r3*.?:

OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the modes and at the frequencies shown in Table 4.3-3.

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DESIGN FEATURES 5.6 FUEL STORAGE CRITICALITY - SPENT FUEL 5.6.1.1 The spent fuel storage racks are designed for fuel enriched to 4.0 l

weight percent U-235 and shall be maintained with:

a.

Ak equivalent to less than 0.95 when flooded with unborated gff water, which includes a conservative allowance of 1.42% delta k/k for uncertainties.*

b.

A nominal 10.375 inch center-to-center distance between fuel assemblies placed in the storage racks.

CRITICALITY - NEW FUEL

5. 6.1. 2 The new fuel pit storage racks are designed and shall be maintained with a nominal 21.0 center-to-center distance between new fuel assemblies such that k will not exceed 0.98 when fuel having an enrichment of 4.5 weight eff percent U-235 is in place and optimum achievable moderation is assumed.

New fuel enrichment is limited to 4.0 weight percent as noted in 5.3.1 and 5.6.1.1.

DRAINAGE 5.6.2 The spent fuel pit is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 722 ft.

CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1386 fuel assemblies.

5.7 COMP 0NENT CYCLIC OR TRANSIENT LIMIT 5.7.1 The components identified in Tabie 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.

"For some accident conditions, the presence of dissolved boron in the pool water may be taken into account by applying the double' contingency principle which requires two unlikely, independent, concurrent events to produce a criticality accident.

SEQUOYAH - UNIT 1 5-5 Amendment No. g, 60

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-TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQUOYAH NUCLEAR Pl. ANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE o.bPR-79 e

1.

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

T A.

!The application for amendment by Tennessee Valley Authority (the licensee) dated October 22,1985, complies with the' standards and I

requirements of the Atomic Energy Act of 1954, as amended (the Act),

Land the Comission's rules and regulations set -forth in 10 CFR Chapter I; J

B..

The facility will. operate in conformity with the application, the provisions off the Act, and the-rules and regulations of the j

Commission q.

C..

There is reasonable assurance (i) that the activities authorized by j

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 Comission's regulations; D.

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

defense and security or to the health and safety of the public; and 1

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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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-79 is hereby amended to. read as follows:

(2). Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 52, are hereby-incorporated. in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

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

FOR THE NUCLEAR REGULATORY '60KMISSION q

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John A. Zwolinski, Assistant Director for P ojects TVA Pro ects Division s

Office of Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance: October 19, 1987 1

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ATTACHMENT TO LICENSE AMENDMENT N0. 52-FACILITY'0PERATING LICENSE NO. DPR DOCKET N0. 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 amendnent number and contain marginal lines indicating the area of change. Overleaf pages* are'provided to j'

maintain ' document completeness.

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INSERT'

' REMOVE 3/4 3-41 3/4 3-41 3/4 3-42 3/4 3-42*

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TABLE 3.3-6 (Continued)

ACTION STATEMENTS ACTION 26 -

With the number of OPERABLE. channels less than required by.the Minimum Channels OPERABLE requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 27 -

With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.1.

ACTION 28 -

With the number.of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9.

ACTION 29 -

With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate and maintain operation of the control room emergency ventilation l

system in the recirculation mode of operation.

ACTION 30 -

With the number of OPERABLE Channels less than the Minimum Channels OPERABLE' requirement, restore the inoperable Channel (s) to OPERABLE Status within 7 days, 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 at least HOT SHUTOOWN within the following 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 subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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SEQUOYAH - UNIT 2 3/4 3-42

^

l DESIGN FEATURES i

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5.6 FUEL STORAGE CRITICALITY - SPENT FUEL

5. 6.1.1 The spent fuel storage racks are designed for fuel enriched to 4.0 weight percent U-235 and shall be maintained with:

l A k,ff equivalent to less than 0.95 when flooded with unborated a.

water, which includes a conservative allowance of 1.42% delta k/k for uncertainties.*

b.

A nominal 10.375 ' inch center-to-center distance between fuel assemblies placed in the storage racks.

CRITICALITY - NEW FUEL 5.6.1.2 The new fuel pit storage racks are designed and shall be maintained with a nominal 21.0 inch center-to-center distance between new fuel assemblies such that k will n t exceed 0.98 when fuel having an enrichment of 4.5 weight eff percent U-235 is in place and optimum achievable moderation is assumed.

New fuel enrichment is limited to 4.0 weight percent, as noted in 5.3.1 and 5.6.1.1.

l DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 722 ft.

l CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1386 fuel assemblies.

5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.

^For some accident conditions, the presence of dissolved boron in the pool water may be taken into account by applying the double contingency principle which requires two unlikely, independent, concurrent events to produce a criticality accident.

SEQUOYAH - UNIT 2 5-5 Amendment No. #, 52

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