Text

Amends 241 & 231 to Licenses DPR-77 & DPR-79,respectively, Revising Sequoyah Nuclear Plant TSs by Extending AOT for Plant EDGs from 72 Hours to 7 Days
	ML20198C005
Person / Time
Site:	Sequoyah
Issue date:	12/16/1998
From:	Hebdon F; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML20198C011	List: ML20198C005; ML20198C021;
References
	NUDOCS 9812210266
	Download: ML20198C005 (26)
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U,J'TED STATES l

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NUCLEAR REGUJTORY COMMISSION l

WASHINGTON, D.C. acuwA001

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TENNESSEE VALLEY AUTHORITY DOCKET NO.50-32Z SEQUOYAH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. M1 License No. DPR-77 1.

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

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated August 22,1996, as supplemented on August 27 and October 8,1998, 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 (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 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 a:nendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

4012210266 981216 PDR ADOCR 05000327 P

PDR

4 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 Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 241 are hereby incorporated in the license.. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

Also, the license is amended by deleting Paragraph 2.C.(15) of page 6 of the Facility Operating License DPR-77.*

4.

This license amendment is effective as of its date of issuance, to be implemented no later than 45 days after issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Frederick J. Hebdo, Director Project Directorate ll-3 Division of Reactor Projects -l/ll Office of Nuclear Reactor Regulation Attachment : 1. Page 6 of License DPR-77

2. Changes to the Technical Specifications Date of issuance: Decerber 16,1998

Page 6 is attached for the composite license to reflect this change.

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(c)

By no later than June 30,1982, all safety related electrical equipment in the facility shail be qualified in accordance with the provisions of: Division of Operating Reactors " Guidelines for Evaluating Environmental l

l Qualification of Class IE Electrical Equipment in Operating Reactos" (DOR Ge!6!ines); or, NUREG4588, " Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment,' December 1879.

Copies of these documents are attached to the Order for Modification of

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Ucence OPR 77 dated November 6,1980. ~

(13)

Loss of Non-Class IE Instrumentation and Control Room Svstem Bus Durina l

Operation (Section 7.10) l l

Prior to exceeding five percent power, TVA must complete revisions to plant j

emergency procedures to the satisfaction of the NRC.

(14)

Enoineerina Safety Feature (ESF) Reset Controls (Section 7.11) i in conformance with IE Bullethi 80-06, TVA shall test the system to identify any t

further areas of concern, and TVA shall review the control schemes to determine that they are the best in terms of equipment control and plant safety. The l

results of these test and review efforts shall be provided to the NRC in l

accordance with the bulletin.

l (15)

This specification has been deleted l

(16)

Fire Protection TVA shallimplement and maintain in effect all provisions of the approved fire l

i protection program referenced in Sequoyah Nuclear Plant's Final Safety Analysis l

Report and as approved in NRC Safety Evaluation Reports contained in l

NUREG-0011, Supplements 1, 2, and 5, NUREG-1232, Volume 2, NRC letters l

dated May 29 and October 6,1986, and the Safety Evaluation issued on l R231 August 12,1997, for License Amendment No. 227, subject to the following l

provision:

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TVA may make changes to the approved fire protection program without l

l prior approval of the Commission only if those changes would not l

adversely affect the ability to achieve and maintain safe shutdown in the l

event of a fire.

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l Amendment 97127,P41 i

e-ATTACHMENTTO LICENSE AMENDMENT NO. 241 i

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 marginallines indicating the areas of change, REMOVE INSERT 3/4 8-1 3/4 8-1 3/4 8-6 3/4 8-6 3/4 8-8 3/4 8-8 B 3/4 0-2 B 3/4 0-2 B 3/4 8-1 B 3/4 8-1 B 3/4 8-ia B 3/4 8-1a 6-10a 6-10a 6-13a 6-13a 6-14 6-14 i

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3/4.8 ELECTRT. CAL POWER SYSTEMS i

3/4.8.1 A.C. JOURCES I

OPERATING LIMITING CONDITION FOR OPERATION l

4 3.8.1.1 As a minimum, the following A.C. electrical power sources shall be OPERABLE:

j a.

Two physically independent circuits between the offsite transmission network and the onsite Class 1E distribution system, ud

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b.

Four separate and independent diesel generator sets each with:

1.

Two diesels driving a common generator 2.

Two engine-mounted fuel tanks containing a minimum volume of 4

250 gallons of fuel, per tank l

3.

A separate fuel storage system containing a minimum volume of 62,000 gallons of fuel, 4.

A separate fuel transfer pump, and 5.

A separate 125-volt D.C. distribution panel, 125-volt D.C.

battery bank and associated charger.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

a.

With one offsite A.C. circuit of the above required A.C. electrical power source inoperable, demonstrate the OPERABILITY of the remaining offsite A.C. circuit by performing Surveillance Requirement 4.8.1.1.1.a within one hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter. Restore at j

least two offsite circuits to OPERABLE statue within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-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 ud in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.#

With diesel generator set (s) IA-A and/or 2A-A or 1B-B and/or 2B-B of the above required A.C.

electrical power sources inoperable,* demonstrate the OPERABILITY cf the remaining A.C.

sources by performing Surveillance Requirement 4.8.1.1.1.a within one hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter, and determining OPERABLE diesel generator sets are not inoperable due to comon cause failure or performing Surveillance Requirement 4.8.1.1.2.a.4 within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; restore at least four diesel generator sets to OPERABLE status within 7 days 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 SNUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

Required actions, to verify OPERABLE diesel generator eats are not inoperable due to comanon cause f ailure or perform SR 4.8.1.1.2.a.4, shall be completed if this action is entered.

No more than one diesel generator may be made simultaneously inoperable on a pre-planned basis for maintenance, modification, or surveillance testing.

SEQUOYAH - UNIT 1 3/4 8-1 Amendment No. IDFfI37723h265, P41

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s ELECTRICAL POWER SYSTEMS l

SURVEILLANCE REQUIREMENTS (Continued) 3.

Verifying the diesel generator operates for at least 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

During the first 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to 2.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months of thi's test, the diesel generator shall be loaded between 4620 kw and 4840 kw and R177 between 2380 kvar and 2600 kvar and during the remaining hours of this test, the diesel generator shall be loaded between 3960 kw and 4400 kw and between 2140 kvar and 2370 kvar.

i The generator voltage and frequency shall be = 6800 volts and a 58.8 Hz within 10 seconds after the start signal. After R238 i

energization, the steady state generator voltage and frquency shall be maintained a 6800 volts and a 7260 volts and a 58.8 Hz and a 61.2 Hz during this test.

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Within 5 minutes of shutting down the diesel generator after it j

has operated a 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded between 3960 kw and 4400 kw and

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between 2140 kvar and 2370 kvar, verify that the diesel R238 l

generator starts within 10 seconds after receipt of the start signal and operates for greater than or equal to 5 minutes.

After energization, the steady state voltage and frequency shall be maintained a 6800 volts and s 7260 volts and a 58.8 Hz and s 61.2 Hz during this test.

l 4.8.1.1.3 The 125-volt D.C. distribution panel, 125-volt D.C. battery bank and l

associated charger for each diesel generator shall be demonstrated OPERABLE:

l a.

At least once per 7 days by verifying:

1.

That the parameters in Table 4.8-la meet the Category A limits.

2.

That the total battery terminal voltage is greater than or equal l

to 124-volts on float charge.

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b.

At least once per 92 days by:

1.

Verifying that the parameters in Table 4.8-la meet the Category I

B limits, 2.

Verifying there is no visible corrosion at either terminals or connectors, or the cell to terminal connection resistance of these items is less than 150 x 10

ohms, and 3.

Verifying that the average electrolyte temperature of 6 connected cells is above 60*F.

lR217 c.

At least once per le months by verifying that:

l 1.

The cells, cell plates and battery racks show no visual indication of physical damage or abnormal deterioration.

2.

The battery to battery and terminal connections are clean, tight and coated with anti-corrosion material.

3.

The resistance of each cell to terminal connection is less than or equal to 150 x 10

ohms.

4.8.1.1.4 This surveillance has been deleted.

SEQUOYAH - UNIT 1 3/4 8-6 Amendment Nos. 52,--iMr--143,

-313 --234,241 2

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ELECTRICAL POWER SYSTEMS SHUTDOWN I

i LIMITING CONDITION FOR OPERATION i

3.8.1.2 As a minimum, the following A.C. electrical power sources shall be OPERABLE:

s.

One circuit between the offsite transmission network and the onsite Class 1E distribution system, and b.

Diesel generator sets 1A-A and 2A-A or 1B-B and 2B-B each with:

1.

Two diesels driving a comon generator, 2.

Two engine-mounted fuel tanks containing a minimum volume of 250 gallons of fuel per tank, 3.

A fuel storage system containing a minimum volume of 62,000 gallons of fuel, 4.

A fuel transfer pump, and 5.

A separate 125-volt D.C. distribution panel, 125-volt D.C.

Nattery bank and associated charger.

APPLICABILITY:

40 DES 5 and 6.

ACTION:

With less than the above minimum required A.C. electrical power sources OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

SURVEILLANCE REQUIREMENTS 4.8.1.2 The above' required A.C. electrical power sources shall be demon-strated OPERABLE by the performance of each of the Surveillance Requirements of 4.8.1.1.1 and 4.8.1.1.2 (except for requirement 4.8.1.1.2.a.5), and 4.8.1.1.3.

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SEQUOYAH - UNIT 1 3/4 8-8 Amendment No. p4j

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l APPLICABILITY BASES 1

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3.0.5 This specification delineates what additional conditi~ons must be j

satisfied to permit operation to continue, consistant'with the ACTION statements for power sources, when a normal or emergency power source is not a

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OPERABLE.

It specifically prohibits operation when one division is inoperable because its normal or emergency power soy'rce is inoperable and a system, i

subsystem, train, component or device in another division is inoperable for another reasor.

l The provisions of this specification permit the ACTION statements associated j

with individual systems, subsystems, trains, components, or devices to be consistent with the ACTION statements of the associated electrical power j

source.

It allows operation to be governed by the time limits of the ACTION statement associated with the Limiting condition for Operation for the normal

i or emergency pover source, not the individual ACTION statements for each system, subsystem, train, component or device that is determined to be i

inoperable solely because of the inoperability of its normal or emergency power source.

3 For example, Specification 3.8.1.1 requires in part that four emergency diesel j

generators be OPERABLE.

The ACTION statement provides for a 7-day out-of-l service time when one emergency diesel generator is not OPERABLE.

If the l

definition of OPERABLE were applied without consideration of specification 3.0.5, all systems, subsystems, trains, components and devices j

supplied by the inoperable emergency power source would also be inoperable.

j This would dictate invoking the applicable ACTION statements for each of the applicable Limiting Conditions for Operation. However, the provisions of 4

specification 3.0.5 permit the time limits for continued operation to be l

consistent with the ACTION statement for the inoperable emergency diesel generator instead, provided the other specified conditions are satisfied.

In 4

this case, this would mean that the corresponding normal power source must be

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OPERABLE, and all redundant systems, subsystems, trains, components, and 1

devices must be OPERABLE, or otherwise satisfy Specification 3.0.5 (i.e., be capable of performing their design function and have at least one normal or one i

emergency power source OPERABLE).

If they are not satisfied, action is I

required in accordance with this specification.

.As a further example, specification 3 B.1.1 requires in part that two physically independent circuits between the offsite transmission network and the onsite class IE distribution system be OPERABLE. The ACTION statement provides a 24-hour out-of-service time when both required offsite circuits are not OPERABLE.

If the definition of OPERABLE were applied without consideration of specification 3.0.5, all systems, subsystems, trains, components and devices supplied by the inoperable normal power sources, both of the offsite circuits, would also be inoperable.

This would dictate invoking the applicable ACTION statements for each of the applicable LCOs. However, the provisions of specification 3.0.5 permit the time limit for continued operation to be consistent with the ACTION statement for the inoperable normal power sources i

SEQUOYAH-UNIT 1 B 3/4 0-2 Amendment No. 241 j

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l 3/4.8 ELECTRICAL POWER SYSTEMS BASES 3/4.8.1 and 3/4.8.2 A.C.

SOURCES AND ONSITE POWER DISTRIBUTION SYSTEMS The OPERABILITY of the A.C. and D.C power sources and associated distri-bution systems during operation ensures that sufficient power will be available to supply the safety related equipment required for 1) the safe shutdown of the facility and 2) the mitigation and control of accident conditions within the facility.

The minimum specified independent and redundant A.C. and D.C. power sources and distribution systems satisfy the requirements of Oeneral Design Criteria 17 of Appendix "A" to 10 CFR 50.

The ACTION requirements specified for the levels of degradation of the power sources provide restriction upon continued facility operation commen-i surate with the level of degradation. The OPERABILITY of the power sources are consistent with the initial condition r.ssumptions of the accident analyses and are based upon maintaining at least one redundant set of onsite A.C. and D.C.

power sources and associated distribution systems OPERABLE during' ingle failure accident conditions coincident with an assumed loss of offsite power and s of the other onsite A.C.

source. When applying Action b of LCO 3.8.1.1, the Configuration Risk Management Program described in Section 6.8.4.i is required to be implemented.

The footnote for Action b of LCO 3.8.1.1 requires completion of a R209 determination that the OPERABLE diesel generators are not inoperable due to common cause failure or performance of Surveillance 4.8.1.1.2.a.4 if Action b is entered. The intent is that all diesel generator inoperabilities must be investigated for common cause failures regardless of how long the diesel generator inoperability persists.

The action to determine that the OPERABLE diesel generators are not inoperable due to common cause failure provides an allowance to avoid unnecessary testing of OPERABLE diesel generators.

If it can be determined, that the cause of the inoperable diesel generator does not exist on the OPERABLE diesel generators, Surveillance Requirement 4.8.1.1.2.a.4 does not have to be performed.

If the cause of inoperability exists on other diesel generator (s), the other diesel generator (s) would be declared inoperable upon discovery and Action e of LCO 3.8.1.1 would be entered as applicable. Once the common failure is repaired, the common cause no longer exists, and the action to determine inoperability due to common cause failure is satisfied.

If the cause of the initial inoperable diesel generator cannot be confirmed not to exist on the remaining diesel generators, performance of Surveillance 4.8.1.1.2.a.4 suffices to provide assurance to continued OPERABILITY of the other diesel generators.

According to Generic Letter 84-15, 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months is reasonable to confirm that the OPERABLE diesel generators are not affected by the same problem as the inoperable diesel generator.

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SEQUOYAH - UNIT 1 B 3/4 8-1 Amendment No.

It,--it?--+73 -

209,bl

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3/4.0 MRCTRICAL POWER SYSTDfS l

RASES 3 /4. s.1 and 3 /4. 8. 2 A.C.

SOURCES AND ONSITE POWER DISTRIBUTION SYSTEMS l

The OPERABILITY of the minimum specified A.C. and D.C. Power sources and associated distribution systems during shutdown and refueling ensures that 1) the facility can be maintained in the shutdown or refueling condition for extended time periods and 2) sufficient instrumentation and control capability l

is available for monitoring and maintaining the unit status.

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The Surveillance Requirements for demonstrating the OPERABILITY of the diesel generators are in accordance with the recomendations of Regulatory Guides 1.9 " Selection of Diesel Generator Set Capacity for Standby Power Supplies," March 10, 1971, and 1.108 " Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants,"

Revision 1, August 1977, and 1.137 " Fuel-Oil Systems for Standby Diesel Generators," Revision 1, October 1979. The surveillance requirements for the diesel generator load-run test and the 24-hour endurance and margin test are in accordance with Regulatory Guide 1.9, Revision 3, July 1993, " Selection, Design, Qualification, and Testing of Emergency Diesel Generator Units Used as R177 Class IE Onsite Electric Power Systems at Nuclear Power Plants." During the diesel generator endurance and margin surveillance test, momentary transients outside the kw and kvar load ranges to not invalidate the test results.

Similarly, during the diesel generator load-run test, momentary transients outside the kw load range do not invalidate the test results.

l Where the SRs discussed herein specify voltage and frequency tolerances, the following is applicable.

6800 volts is the minimum steady state output voltage and the 10 second transient value.

6800 volts is 98.6% of nominal bus voltage of 6900 volts and is based on the minimum voltage required for the R238 diesel generator supply breaker to close on the 6.9 kV shutdown board. The specified maximum steady state output voltage of 7260 volts is based on the degraded over voltage relay setpoint and is equivalent to 110% of the nameplate rating of the 6600 volt motors. The specified minimum and maximum frequencies of the diesel generator are 58.8 Hz and 61.2 Hz, respectively. These values are equal to i 2% of the 60 Hz nominal frequency and are derived from the recommendations given in regulatory Guide 1.9.

The Surveillance Requirement for demonstrating the OPERABILITY of the Station batteries are based on the recommendations of Regulatory Guide 1.129

" Maintenance Testing and Replacetuent of Large Lead Storage Batteries for Nuclear Power Plants,* February 1978, and IEEE 3td 450-1980, "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Large Lead Storage Batteries for Generating Stations and Substations."

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f SEQUOYAH - UNIT 1 B 3/4 8-la Amendment No. 121--15h--1+3 209 20s, M4,241 i

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ADMINISTRATIVE CONTROLS R221 h.

Containment Leakage Rate Testing

Program A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54 (o) and 10 CFR 50 Appendix J, Option B, as modified by approved exemptions. Visual examination and testing, including test intervals and extensions, shall be in accordance with Regulatory Guide (RG) 1.163,

" Performance-Based Containment Leak-Test Program," dated September 1995 with exceptions provided in the site implementing instructions.

The peak calculated containment internal pressure for the design basis loss of coolant accident, P.,

is 12.0 psig.

The maximum allowable containment leakage rate, Eg, at P,,

is 0.25% of the primary containment air weight per day.

Leakage rate acceptance criteria are:

a.

Containment overall leakage rate acceptance criteria is s 1.0 L,.

During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are s 0. 6 0 Lg for the combined Type B and Type C tests, and s 0.75 L, for Type A tests; b.

Air lock testing acceptance criteria are:

1)

Overall air lock leakage rate is s 0. 0 5 Lg when tested at a P..

2)

For each door, leakage rate is s 0. 01 Ig when pressurized to a 6 psig for at least two minutes.

The provisions of SR 4.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.

The provisions of SR 4.0.3 are applicable to the Containment Leakage Rate Testing Program, i.

Configuration Risk Management Program The Configuration Risk Management Program (CRMP) provides a proceduralized risk-informed assessment to manage the risk associated with equipment inoperability. The program applies to Technical Specification structures, systems, or components for which a risk-informed allowed outage time has been granted.

The program shall include the following elements:

a.

Provisions for the control and implementation of a Level 1 at-power internal events PRA-informed methodology. The assessment shall be capable of evaluating the applicable plant configuration.

b.

Provisions fo. performing an assessment prior to entering the Limiting Condits'.n for Operation (LCO) Action for preplanned activities.

c.

Provisions for performing an assessment after entering the LCO Action for unplanned entry into the LCO Action.

d.

Provisions for assessing the need for additional actions after the discovery of additional equipment out of service conditions while in the LCO Action, e.

Provisions for considering other applicable risk significant contributors such as Level 2 issues and external events, qualitatively or quantitatively.

f SEQUOYAH - UNIT 1 6-10a Amendment No. 21~A,241

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ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (continued) 6.

WCAP-10054-P-A, Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code, August 1985, (E Proprietary)

(Methodology for Specification 3/4.2.2 - Heat Flux Hot N nnel Factor) 7.

WCAP-10266-P-A, Rev. 2, "THE 1981 REVISION OF WESTINGHOUSE EVALUATION R227 MODEL USING BASH CODE", Ma'ch 1987, (E Proprietary).

(Methodology for SpecAfication 3.2.2 - Heat Flux Hot Channel Factor).

6.9.1.14.b The core operating limits shall be determined so that all applicable limits (e.g., fuel therinal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transiant and accident analysis limits) of the safety analysis are met.

6.9.1.14.c THE CORE OPERATING LIMITS REPORT shall be provided within 30 days after cycle start-up (Mode 2) for each reload cycle or within 30 days of R159 issuance of any midcycle revision of the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.

SPECIAL REPORTS 6.9.2.1 Special reports shall be submitted within the time period specified R76 for each report, in accordance with 10 CFR 50.4.

6.9.2.2 This specification has been deleted.

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SEQUOYAH - UNIT 1 6-13a Amendment No. 12, 99, 99,

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-ku, 455, ses,241 i

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ADMINISTRATIVE CONTROLS I

6.10 RECORD RETENTION (DELETED)

R237 b

SEQUOYAH - UNIT 1 6-14 Amendment No. M, Sh 59, M, 427, ats, M3, M(, :Ltt, 337241

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UNITED STATES g

j NUCLEAR REGULATORY COMMISSION 2

WASHINGTON, D.C. 206664 201 p%{ @T /

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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 231 License No. DPR-79 1.

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

l A.

The application for amendment by Tennessee Valley Authority (the licensee) dated August 22,1996, as supplemented on August 27 and October 8,1998, 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 (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 be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and i

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.

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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-79 is hereby amended to read as follows:

(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.231 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

1

3. -

Also, the license is amended by deleting Paragraph 2.C.(12) of page 5 of the Facility

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Operating License DPR-79

4.

This license amendment is effective as of its date of issuance, to be implemented no later than 45 days after issuance.

FOR THE NUCLEAR REGULATORY COMMISSION G

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Frederick J. Hebdon, rector l

Project Directorate 11-3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Attachment : 1. Page 5 of License DPR-79 l

2. Changes to the Technical l

Specifications Date of Issuance: Decerber 16, 1998 l

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Page 5 is attached, for the composite license to reflect this change.

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m 1 b.

Complete and auditable records must be available and l

maintained at a central location which describe the l

environmental qualification method used for all safety-related electrical equipment in. sufficient detail to document the degree of compliance with the DOR Guidelines or NUREG-0588.

Such records should be updated and maintained current as equipment is replaced, further tested, or otherwise further qualified to document complete compliance by June 30, 1982.

c.

Within 90 days of receipt of the equipment qualification safety evaluation, the licensee shall either (1) provide missing documentation identified in Sections 3 and 4 of the equipment qualification safety evaluation which will demonstrate compliance of the applicable equipment with NUREG-0588, or (ii) commit to corrective actions which will result in documentation of compliance of applicable equipment with NUREG-0588 no later than June 30, 1982.

(11)

Recuirements For Modification To Or Addition Of Instrumentation And Controls (Section 7.3.2) a.

Prior to startup after first refueling, TVA shall have installed instrument downscale failure alarus for the effluent monitoring instrumentation channels for l

radioactive gaseous and radioactive liquid effluentse R2 Modifications to procedures and Technical Specifications 3.3.3.9 and 3.3.3.10 shall have been completed.

b.

Prior to startup after the first refueling, TVA shall have received NRC approval of an additional operable level of over/undervoltage protection including associated Technical Specifications. The level of protection from the effects of power transients on safety-related equipment provided by Part I of the staff's " Degraded Grid voltage Position", or equivalent, is required.

(12)

This specification has been deleted.

Amendment 2,231 l

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ATTACHMENT TO LICENSE AMENDMENT NO. 231 FACILITY OPERATING LICENSE NO. DPR-79 j

DOCKET NO. 50-328 Revise the Appendix A Technical Specifications,, removing the pages identified below and inserting the enclosed pages. The revised pages

? identified by the captioned amendment number and contain marginal lines indicating the r,reas of change.

REMOVE INEiBI 3/4 8-1 3/4 8-1 i

3/4 8-7 3/4 6-7 3/4 8-9 3/4 8-9 B 3/4 0-2 B 3/4 0-2 B 3/4 8-1 B 3/4 8-1 B 3/4 8-ia B 3/4 8-1a 6-10 6-10 6-14 6-14 6-15 6-15

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3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C.

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OPERATING LIMITING CONDITION FOR OPERATION l

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3.8.1.1 As a mir.imum, the following A.C. electrical power sources shall be OPERABLE:

a.

Two physically independent. circuits between the offsite transmission t.etwork and the onsite Class 1E distribution system, l

and b.

Four separate and independent diesel generator sets each with:

1.

Two diesels driving a common generator 2.

Two engine-mounted fuel tanks containing a minimum volume of 250 gallons of fuel, per tank 3.

A separate fuel storage system containing a minimum volume of 62,000 gallons of fuel, 4.

A separate fuel transfer pump, and 5.

A separate 125-volt D.C. distribution panel, 125-volt D.C.

battery bank and associated charger.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTIONt With one offsite A.C. circuit of the above required A.C.

electrical a.

power source inoperable, demonstrate the OPERABILITY of the remaining offsite A.C. circuit by performing Surveillance Requirement 4.8.1.1.1.a within one hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

Restore at least two offsite circuits to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-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 SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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With diesel generator set (s) IA-A and/or 2A-A or 1B-B and/or 2B-B of the above required A.C.

electrical power sources inoperable,* demonstrate the OPERABILITY of the remaining A.C.

sources by performing Surveillance Requirement 4.8.1.1.1.a within one hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter, and determining OPERABLE diesel generator sets are not inoperable due to comon cause failure or performing Surveillance Requirement 4.8.1.1.2.a.4 within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; restore at least four diesel generator sets to OPERABLE status within 7 days 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 SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

l Required actions, to verify OPERABLE diesel generator sets are not inoperable due to common cause failure or perform SR 4.8.1.1.2.a.4, shall be completed if this action is entered.

No more than one diesel generator may be ma.de simultaneously inoperable on a pre-planned basis for maintenance, modification, or surveillance testing.

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l SEQUOYAH - UNIT 2 3/4 8-1 Amendment No. 89.119.193,129,231 1

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ELECTRICAL POWER SYSTEMS 4'

SURVIILIANCE REQUIREMENTS (Continued) 4.8.1.1.4 This surveillance has been deleted.

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SEQUOYAH - UNIT 2 3/4 8-7 Amendment No. 44,231

i ELECTRICAL POWER SYSTEMS SHITTDOWN LIMITING CONDITION FOR OPERATION 333y 3.8.1 2 As a minimum, the following A.C. electrical power scurces shall be OPERABLE:

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a.

One circuit between the offsite transmission network and the onsite Class lE distribution'aystem, and b.

Diesel generator sets lA-A and 2A-A or 1B-B and 2B-B each with:

1.

Two diesels driving a common generator, 2.

Two engine-mounted fuel tanks containing a miniw.un volume of 250 gallons of fuel per tank, 3.

A fuel storage system containing a minimum volume of 62,000 gallons of fuel, 4.

A fuel transfer pump, and 5.

A separate 125-volt D.C. distribution panel, 125-volt D.C.

battery bank and associated charger.

APPLICABILITY: MODES 5 and 6.

ACTION:

With less than the above minimum required A.C. electrical power sources OPERABLE, suspend all operations involving CORE ALTERATIONS cr positive reactivity changes.

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i 1-i SURVEILLANCE REQUIREMENTS 4.8.1.2 The above required A.C. electrical power sources shall be demon-strated OPERABLE by the performance of each of the Surveillance Requirements of 4.8.1.1.1 and 4.8.1.1.2 (except for requirement 4.8.1.1.2.a.5), and 4.8.1.1.3.

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SEQUOYAH - UNIT 2 3/4 C-9 Amendment No. 231

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l BASES 3. 0. !i This specification delineates what additional conditions must be satisfied to permit operation to continue, consistent with the ACTION state-ments for power sources, when a normal or emergency power source is not OPERASLE.

It specifically prohibits operation when one divi'sion is '

srable because its normal er emergency power source is inoperable and a sysup, subsystem, train, component or device in another division is inoperable for another rencon.

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The provisiens of this specification permit the ACTION statements associated with individual systans, subsystems, trains, components, or devices to be I

consistent with the ACTION statements of the associated electrical power j

source.

It allows operat.Lon to be governed by the time limits of the ACTION statement associated with the Limiting Condition for Operation for the normal l

l or emezgency power source, not the individual ACTION statements for each system, subsystem, tre,in, component. or device that is determined to be l

inoperable solely heemuse of the inoperability of its normal or emergency power source.

For example, Specification 3.8.1.1 requires in part that four emergency diesel generators be OPERABLE. The ACTION statement provides for a 7-day out-of-l service time when one emergency diesel generator is not OPERABLE.

If the definition of OPERABLE were applied without consideration of Specification 3.0.5, all systems, subsystems, trains, components and devices supplied by the inoperable emergency power. source would also be inoperable.

This would dictate invoking the applicablo ACTION statements for each of the applicable Limiting Conditions fer Operation. However, the provisions of Specification 3.0.5 permit the time limits for continued operation to be l

consistent stith the ACTION statement for the inoperable emergency diesel generator instead, provided the other speci2ied conditions are satisfied.

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this c.nse, thi:1 would mean ths.t the corresponding nornal power source must be 1

OPERA EE, and all redundant systems, s bsystems, trains, components, and devices must be OPERABLE, or otherwise satisfy Specification 3.0.5 (i.e., be capable of performing their design function and have at least one normal or one emergency power source OPERABLT).

If they are not satisfied, action is i

required in accordance with thi:s specificcticn.

l As a further example, specification 3.8.1.1 requires in part that two physical.*ty independent circuits between the offsite transmission network and the ensite Class IE distribution system be OPERABLE.

The ACTION statement providen a 34-hour out-of-service tire when both required effsite circuits are not OPERABLE.

If the defiattion of OPERABLE were applied without consideration of Specification 3.0.5, all systems, subsystems, trains, components and devices supplied by the inoperable normal power sources, both of the offsite circuits, would also be inoperable. This would dictate invoking the applicable ACTION statements for each of the applicable LCOs. However, the provisions of Specification 3.0.5 perrdt the tire limit for continued operation to be consistent with the ACTION stateteent for the inoperable normal power sources instead, provided the other l

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l SEQUOYAH - UNIT 2 B 3/4 0-2 Amendment No. 231 1

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3/4.0 ELECTRICAL PC-?R SYSTEMS BASES 3/4.8.1 AND 3/4.8.2 A.C.

SOURCES AND ONSITE POWER DISTRIBUTION SYSTEMS The OPERABILITY of the A.C. and D.C power sources and associated distribution systems during operation ensures that sufficient power will be available to supply the safety related equipment required for 1) the safe shutdown of the facility and 2) the mitigation and control of accident condi-tions within the facility. The minimum specified independent and redundant A.C. and D.C. power sources and distribution systems satisfy the requirements of General Design Criterion 17 of Appendix "A" to 10 CFR 50.

The ACTION requirements specified for the levels of degradation of the power sources provide restriction upon continued facility operation l

commensurate with the level of degradation. The OPERABILITY of the power i

sources are consistent with the initial condition assumptions of the safety analyses and are based upon maintaining at least one redundant set of onsite A.C. and D.C. power sources and associated distribution systems OPERABLE during accident conditions coincident with an assumed loss of offsite power and single failure of the other onsite A.C.

source. When applying Action b of LCO 3.8.1.1, the Configuration Risk Management Program described in Section 6.8.4.i i

is required to be implemented.

The footnote for Action b of LCO 3.8.1.1 requires completion of a determination that the OPERABLE diesel generators are not inoperable due to common cause failure or performance of Surveillance 4.8.1.1.2.a.4 if Action b is entered.

The intent is that all diesel generator inoperabilities must be investigated for common cause failures regardless of how long the diesel R195 generator inoperability persists, The action to determine that the OPERABLE diesel generators are not inoperable due to common cause failures provides an allowance to avoid unnecessary testing of OPERABLE diesel generators.

If it can be determined that the cause of the inoperable diesel generator does not exist on the OPERABLE diesel generators, Surveillance Require.aent 4.8.1.1.2.a.4 does not have to be performed.

If the cause of inoperability exists on other diesel generator (s), the other diesel generator (s) would be declared inoperable upon discovery and Action e of LCO 3.8.1.1 would be entered as applicable. Once the common failure is repaired, the common cause no longer exists, and the action to determine inoperability due to common cause failure is satisfied.

If the cause of the initial inoperable diesel generator cannot be confirmed not to exist on the remaining diesel generators, performance of Surveillance 4.8.1.1.2.a.4 suffices to provide assurance of continued OPERABILITY of the other diesel generators.

According to Generic Letter 84-15, 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months is reasonable to confirm that the OPERABLE diesel generators are not affected by the same problem as the t

inoperable diesel generator.

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SEQUOYAH - UNIT 2 B 3/4 8-1 Amendment No.

19+---l-64---3-95, 231

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_._________.______________.m 3/4.8 m JCTRICAL POWER SYSTEMS BASES 3/4.8.1 AND 3/4.8.2 A.C.

SOURCES AND ONSITE POWER DISTRIBUTION SYSTEMS The OPERABILITY of the minimum specified A.C. and D.C. power sources and associated distribution systems during shutdown and refueling ensures that

1) the facility can be maintained in the. shutdown er refueling condition for extended time periods and 2) sufficient instrumentation and control capability is available for monitoring and maintaining the unit status.

The Surveillance Requirements for demonstrating the OPERABILITY of the diesel ganerators are in accordance with the recommendations of Regulatory Guides 1.9 " Selection of Diesel Generator Set Capacity for Standby Power Supplies", March 10, 1971, 1.108 " Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants," Revision 1, August 1977, and 1.137 " Fuel-Oil Systems for Standby Diesel Generators,"

Revision 1, October 1979.

The surveillance requirements for the diesel generator load-run test and the 24-hour endurance and margin test are in accordance with Regulatory Guide 1.9, Revision 3, July 1993, " Selection, Design, Qualification, and Testing of Emergency Diesel Generator Units Used as l

Class 1E Onsite Electric Power Systems at Nuclear Power Plant."

During the R164 diesel generator endurance and margin surveillance test, momentary transients outside the kw and kvar load ranges do not invalidate the test results.

Similarly, during the diesel generator load-run test, momentary transients outside the kw load range do not invalidate the test results.

Where the SRs discussed herein specify voltage and frequency tolerances, the following is applicable.

6800 volts is the minimum steady state output voltage and the 10 second transient value.

6800 volts is 98.6% of nominal bus voltage of 6900 volts and is based on the minimum voltage required for the R224 diesel generator supply breaker to close on the 6.9 kV shutdown board. The specified maximum steady state output voltage of 7260 volts is based on the degraded over voltage relay setpoint and is equivalent to 110% of the nameplate rating of the 6600 volt motors. The specified minimum and maximum frequencies l

of the diesel generator are 58.8 Hz and 61.2 Hz, respectively. These values are equal to i 2% of the 60 Hz nominal frequency and are derived from the recommendations given in regulatory Guide 1.9.

The Surveillance Requirement for demonstrating the OPERABILITY of the Station batteries are are based on the recommendations of Regulatory Guide 1.129 " Maintenance Testing and Replacement of Large Lead Storage Batteries for Nuclear Power Plants," February 1978, and IEEE Std 450-1980, "IEEE Recomended Practice for Maintenance, Testing and Replacement of Large Lead Storage Batteries for Generating Stations and Substations."

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i SEQUOYAH - UNIT 2 B 3/4 8-la Amendment No. 3-2h--164 r-145, lR195 E' -

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ADMINISTRATIVE CONTROLS l

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Air lock testing acceptance criteria are:

1)

Overall air lock leakage rate is s 0.05 L, when tested at a P.

2)

For each door, leakage rate is s 0.01 L, when pressurized to R207

= 6 psig for at least two minutes.

The provisions of SR 4.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.

The provisions of SR 4.0.3 are applicable to the Containment Leakage Rate Testing Program.

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Configuration Risk Management Procram The Configuration Risk Management Program (CRMP) provides a proceduralized risk-informed assessment to manage the risk associated with equipment inoperability. The program applies to Technical Specification structures, systems, or components for which a risk-informed allowed outage time has been granted.

The program shall include the following elements:

a.

Provisions for the control and implementation of.a Level 1 at-power internal events PRA-informed methodology. The assessment shall be capable of evaluating the applicable plant configuration.

b.

Provisions for performing an assessment prior to entering the Limiting Condition for Operation (LCO) Action for preplanned activities.

c.

Provisions'for performing an assessment after entering the LCO Action for unplanned entry into the LCO Action, d.

Provisions for assessing the need for additional actions after the discovery of additional equipment out of service conditipns while in the LCO Action, e.

Provisions for considering other applicable risk significant contributors such as Level 2 issues and external events, qualitatively or quantitatively.

6.9 REPORTING REOUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted in accordance R64 with 10 CFR 50.4.

STARTUP REPORT I

6.9.1.1 DELETED 6.9.1.2 DELETED R223 6.9.1.3 DELETED l

SEQUOYAH - UNIT 2 6-10 Amendment No.1Mrr-ter 64.M4, 7

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l ADMINISTRATIVE CONTROLS CORE OPEkATING LIMITS REPORT (continued) l l

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WCAP-10054-P-A, Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code, August 1985, (E Proprietary)

(Methodology for specification 3/4.2.2 - Heat Flux Hot Channel Factor)

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WCAP-10266-P-A, Rev. 2, "THE 1981 REVISION OF WESTINGHOUSE EVALUATION l

MODEL USING BASH CODE", March 1987, (E Proprietary).

l (Methodology for Specification 3.2.2 - Heat Flux Hot r'hannel l

Factor).

6.9.1.14.b The core operating limits shall be detemined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.

R146 6.9.1.14.c THE CORE OPERATING LIMITS REPORT shall be provided within 30 days l

after cycle start-up (Mode 2) for each reload cycle or within 30 days of issuance of any midcycle revision of the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.

j SPECIAL REPORTS 6.9.2.1 Special reports shall be submitted within the time period specified for each report, in accordance with 10 CFR 50.4.

R64 6.9.2.2 This specification has been deleted.

I SEQUOYAH - UNIT 2 6-14 Amendment Nos. 44, 59, 6+, 1+

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ADMINISTRATIVE CONTROLS 6.10 RECORD RETENTION (DELETED) lR223 i

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SEQUOYAH - UNIT 2 6-15 Amendment No. 91F, 44, 60, 64, M7, l

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ML20198C005

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