Text

Amends 36 & 28 to Licenses DPR-77 & DPR-79,respectively, Changing Tech Specs Re Unit 2 Operational Temp Limits for Pressurizer Spray Nozzle,Insp of Protective Fuses & Reporting Requirements Under 10CFR50.73
	ML20100B366
Person / Time
Site:	Sequoyah
Issue date:	11/23/1984
From:	Adensam E; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20100B369	List: ML20100B366; ML20100B401;
References
	NUDOCS 8412040317
	Download: ML20100B366 (75)
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UNITED STATES

, y i'.- f' g NUCLEAR REGULATORY COMMISSION w

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E WASHINGTO N, D. C. 20555

_ TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 36 License No. ORP-77 1.

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

A.

The applications for amendment to the Sequoyah Nuclear Plant, Unit 1 (the facility) Facility Operating License No. DPR-77 filed by the Tennessee Valley Authority (licensee), dated September 17, 1982, July 21, 1983, and April 20, 1984, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the license, as amended, the provisions of the Act, and the rules and' regulations of the Com-mission; 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 Consnission's regulations and all applicable requireinents have been satisfied.

2.

Accordingly, the license is hereby amended by page changes to the Appendix A Technical Specifications as indicated in the attachment to this license amend-ment, and paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix'A, as revised through Amendment No. 36, are hereby incorporated into the license.

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4 2-The licensce 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 f/.

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(,fs NC m ),). $dAO' W I

Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing

Attachment:

Appendix A Technical Specification Changes Date of Issuance: November 23, 1984 S

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ATTACHMENT TO LICENSE AMENDMENT NO. 36 FACILITYOPERATINGLIdENSENO.OPR-77 DOCKET NO. 50-327 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.

Amended Page 3/4 4-26 5-6 1-5 3/4 1-4 3/4 3-58 3/4 4-10 3/4 4-12 3/4 4-20 3/4 5-5

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3/4 5-9 3/4 6-11 3/4 6-12 3/4 7-31 3/4 7-33 3/4 7-35 3/4 7-37 3/4 7-41 3/4 11-5 3/4 11-6 3/4 11-12 3/4 11-13 3/4 11-14 3/4 11-17 3/4 11-19 3/4 12-1 3/4 12-10 6-14 6-16 6-19 6-20 6-21 6-22 B3/4 4-3 3/4 6-10 e

9 L_

-o REACTOR COOLANT SYSTEM PRESSURIZER LIMITING CONDITION FOR OPERATION 3.4.9.2 The pressurizer temperature shall be limited to:

a.

A maximum heatup of 100*F in any one hour period, b.

A maximum cooldown of 200*F in any one hour period, and c.

A maximum spray wa.ter temperature differential of 560'F.

APPLICABILITY: At all times.

ACTION:

With the pressurizer temperature limits in excess of any of the above limits, restore the temperature to within the limits within 30 minutes; perform an engineering evaluation to determine the effects of the out-of-limit condition on the structural integrity of the pressurizer; determine that the pressurizer remains acceptable for continued operation 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 reduce the pressurizer pressure to less than 500 psig within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , i

SURVEILLANCE REQUIREMENTS 4.4.9.2.1 The pressurizer temperatures shall be determined to be within the limits at least once per 30 minutes during system heatup or cooldown.

4.4.9.2.2 Any occurrence of spray operation with a differential temperature greater than 320"F shall be recorded for evaluation of the cyclic limits in Table 5.7.1.

SEQUO('H - UNIT I 3/4 4-26 Amendment No. 36

Q TABLE 5.7.1 c

COMPONENT CYCLIC OR TRANSIENT LIMITS 2x CYCLIC OR i

DESIGN CYCLE g

00:1P0rlENT TRANSIENT LIMIT OR TRANSIENT O

Reactor Coolant System 200 heatup cycles at < 100*F/hr Heatup cycle - T**U from < 200*F

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and 200 cooldown cycles at to 2 550*F.

< 100*F/hr Cooldown cycle - T from

> 550*F to < 200*F**9

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200 pressurizer cooldown cycles Pressurizer cooldown cycle at i 200*F/hr

_ temperatures from 1 650*F to 5 200*F.

80 liss of load cycles, without 1 15% of RATED THERMAL POWER to.

immediate turbine or reactor trip.

0% of RATED THERMAL POWER.

T 40 cycles of loss of offsite Luss of offsite A.C. electrical A.C. electrical power.

power source supplying the onsite ESF Electrical; System. -

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i 80 cycles'cf loss of flow in one Loss of only one react (s reactor coolant. loop.

coolant pump.

9'.'

400 reactor trip cycles.

100% to 0% of RATED THERMAL P0w'tR.:

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12 spray actuation cycles.

Spray water temperature' differential

> 320*F and < 560*F.

50 leak tests Pressurized to 2485 psig 5 hydrostatic pressure tests Pressurized to 3105 psig g

m F.

Secondary System' 5 hydrostatic pressurb tests Pressurized to 1330 psig 5

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-o LDEFINITIONS QUADRANT POWER TILT RATIO.

1.22. QUADRANT POWER TILT RATIO.shall be the ratio of the maximum upper excore detector calibrated output to the average of the upper excore detector _ calibrated outputs, or the ratio of the maximum lower excore detector calibrated output

- to the average of the, lower excore detector calibrated outputs, whichever is greater. With one excore detector ' inoperable, the remaining three detectors shall be used for computing the average.

RATED THERMAL POWER 1.23 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3411 MWt.

REACTOR TRIP SYSTEM RESPONSE TIME 1.24 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from-when the monitored parameter exceeds its trip setpoint at the channel sensor until loss of stationary gripper coil voltage.

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REPORTABLE _ EVENT 1.25 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.

SHIELD BUILDING INTEGRITY 1.26 SHIELD BUILDING INTEGRITY shall exist when:

a.

The door in each access opening is closed except when the access opening is being used for normal transit entry and exit.

b.

The emergency gas treatment system is OPERABLE.

c.

The sealing mechanism associated with each penetration (e.g.,_

welds, bellows or 0-rings) is OPERABLE.

SHUIDOVN MARGIN 1.27 SHUTOOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming all full length rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest reactivity worth whlch is assumed to be fully withdrawn.

e 5fC"OtAH - UNIT 1 1-5 Amendmi.nt No.

REACTIVITY CONTROL SYSTEMS 1

MODERATOR TEMPERATURE COEFFICIENT LIMITING CONDITION FOR OPERATION 3.1.1.3 The moderator temperature coefficient (MTC) shall be:

a.

Less positive than 0 delta k/k/ F for the all rods withdrawn, beginning of cycle life (BOL), hot zero THERMAL POWER condition.

~4 b.

Less negative than -4.0 x 10 delta k/k/*F for the all rods with-drawn, end of cycle life (E0L), RATED THERMAL POWER co,dition.

APPLICABILITY:

Specification 3.1.1.3.a - MODES 1 and 2* only#

Specification 3.1.1.3.b - MODES 1, 2 and 3 only#

ACTION:

1 a.

With the MTC more positive than the limit of 3.1.1.3.a above operation in MODES 1 and 2 may proceed provided:

1.

Control rod withdrawal limits are established and maintained sufficient to restore the MTC to less positive than 0 delta k/k/*F within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

These withdrawal limits shall be in addition to the insertion limits of Specification 3.1.3.6.

2.

The control rods are maintained within the withdrawal limits established above until a subsequent calculation verifies that the MTC has been restored to within its limit for the all rods withdrawn condition.

3.

In lieu of any other report required by Specification,6.6.1, a Special Report is. prepared and submitted to the Commission pursuant to Specification 6.9.2 within 10 days, describing the value of the measured MTC, the interim control rod withdrawal limits and the predicted average core burnup necessary for restoring the positive MTC to within its limit for the all rods withdrawn condition.

b.

With the MTC more negative than the limit of 3.1.1.3.b above, be in HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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With K,ff greater than or equal to 1.0

See Special Test Exception 3.10.3 SE000i.J! - UNIT 1 3/4 1-4 Amendment No. 36 J

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e INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 3.3-11 shall be OPERABLF.

' APPLICABILITY:

Whenever equipment protected by the fire detection instrument is required to be OPERABLE.#

ACTION:

With the number of OPERABLE fire detection instrument (s) less than the minimum number OPERABLE requirement of Table 3.3-11:

a.

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour, unless the instrument (s) is located inside the containment, then inspect the containment at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or monitor the containment air temperature at least once per hour at the locations listed in Specification 4.6.1.5.

b.

Restore the inoperable instrument (s) to OPERABLE status within 14 days or, in lieu of any other report required by Specifica-tion 6.6.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the instrument (s) to OPERABLE status.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.8.1 Each of the above required fire detection instruments which are accessible during operation shall be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST.

Fire detection which are not accessible during plant operation shall be demonstrated OPERABLE by the performance of a CHANNEL FUNCTIONAL TEST dur.ing each COLD SHUT 00WN exceeding 24 nours unless performed in the previous 6 months.

4.3.3.8.2 The NFPA Code 72D supervised circuits supervision associated with the detector alarms of each of the above required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months.

4.3.3.8.3 The non-supervised circuits between the local fire protection panels and actuated equipment shall be demonstrated OPERABLE at least once per 6 months.

lhe fire detection instruments located withih the containment are not required to'be 0PERABLE during the performance of Type A Containment Leakage Rate Tests.

MGUOGH - UNIT 1 3/4 3-5" Amendwnt No. M

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) b.

The steam generator shall be determined OPERABLE after completing the corresponding actions (plug all tubes exceeding the plugging limit and all tubes containing through-wall cracks) required by Table 4.4-2.

4.4.5.5 Reports a.

Following each inservice inspection of steam generator tubes, the

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number of tubes plugged in each steam generator shall be reported to the Commission within 15 days, b.

The complete results of the steam generator tube inservice inspection shall be submitted to the Commission in a Special Report pursuant to Specification 6.9.2 within 12 months following completion of the inspection.

This Special Report shall include:

1.

Number and extent of tubes inspected.

2.

Location and percent of wall-thickness penetration for each indication of an imperfection.

3.

Identification of tubes plugged.

c.

Results of steam generator tube inspections which fall into Category C-3 shall be reported pursuant to Specification 6.6.1 prior to resump-tion of plant operation. The written followup of this report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.

SEQ'T..': - UNIT 1 3/4 4-10 Amen.P ent No. 36 9

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,s TABLE 4.4-2 p

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I STEAM GENERATOR TUBE INSPECTION C

=

5 1ST SAMPLE INSPECTION 2ND SAMPLE INSPECTION 3RD SAMPLE INSPECTION Sample Size Result Action Required Result Action Required Result Action Required 4

A minimum of C-1 None N/A-N/A N/A.

N/A*

1 S Tubes per S. G.

C-2 Plug defective tubes C-1 None N/A N/A and inspect additional Plug defective tubes C-1 None 2S tubes in this S. G.

C-2 and inspect additional C-2 Plug defective tubes 4S tubes in this S. G.

Perfo'rm action for l

C-3 C-3 result of first sample i

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Perform action for C-3 C-3 result of first N/A N/A j

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C-3 Inspect all tubes in All other this S. G., plug de-S. G.s are None N/A-N/A fective tubes and C-1 inspect 2S tu in Some S. G.s Perform action for N/A N/A' C-2 but no C-2 result of second additional g

,,,p, Prompt notification S. G. are to NRC pursuant C-4 to specification Additional inspect all tubes in 6.6.1 S. G. is C-3 each S. G. and plug defective tubes.

Pro'mpt notification N/A N/A to NRC pursuant to specification 2,

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6.6.1

=a S = 3 h Where N is the number of steam generators in the unit, and n is the number of steem generators inspected g

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REACTOR COOLANT SYSTEM ACTION:

(Continued)

MODES 1, 2, 3, 4 and 5 With the specific activity of the primary coolant greater than _

a.

l.0 microcuries/ gram DOSE EQUIVALENT I-131 or greater than 100/E

'microcuries/ gram, perform the sampling and analysis requirements of item 4a of Table 4.4-4 until the specific activity of the primary coolant is restored to within its limits.

A SPECIAL REPORT shall be prepared and submitted to the Commission pursuant to Specifica-tion 6.9.2 within 30 days.

This report shall contain the results of the specific activity analyses together with the following information:

1.

Reactor power history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded, 2.

Fuel burnup by core region, 3.

Clean-up flow history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded, 4.

History of de gassing operations, if any, starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded, and

~5.-

The time duration when the specific activity of the primary coolant exceeded 1.0 microcuries/ gram DOSE EQUIVALENT I-131.

SURVEILLANCE REQUIREMENTS 4.4.8 The specific activity of the primary coolant shall be determined to be within the limits by performance of the sampling and analysis program of Table 4.4-4.

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i SE! " t i,H - UNIT 1 3/4 4-20 Amendment No. 36

EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.2 ECCS SUBSYSTEMS - T,y Greater Than or Equal to 350*F LIMITING CONDITION FOR OPERATION 3.5.2 Two independent ECCS subsys.tems shall be OPERABLE with each subsystem comprised of:

a.

One'0PERABLE centrifugal charging pump, b.

One OPERABLE safety injection pump, c.

One OPERABLE residual heat removal heat exchanger, d.

One OPERABLE residual heat removal pump, and e.

An OPERABLE flow path capable of taking suction from the refueling water storage tank on a safety injection signal and automatically tronsferring suction to the containment sump during the recirculation phase of operation.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a.

With one ECCS subsystem inoperable, restore the inoperable subsystem 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

In the event the ECCS is actuated and injects water into the Reactor Coolant System, a REPORTABLE EVENT shall be prepared and submitted to the Commission pursuant to Specification 6.6.1.

This report shall include a description of the circumstances of the actuation and the total accumulated actuation cycles to date.

The current value of the usage factor for each affected safety injection nozzle shall be provided in this report whenever its value exceeds 0.70.

SURVEILLANCE REQUIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:

a.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the following valves are in the indicated positions with power to the valve operators removed:

SECUOYAH - UNIT 1

_3/4 5-5 Amendment No.

36

a EMERGENCY CORE C'00 LING SYSTEMS (ECCS) 3/4.5.3 ECCS SUBSYSTEMS - T,yg Less Than 350 F LIMITING CONDITION FOR OPERATION 3.5.3 As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE:

a.

One OPERABLE centrifugal charging pump, b.

One OPERABLE residual heat removal heat exchanger, c.

One OPERABLE residual heat removal pump, and d.

An OPERABLE flow path capable of taking suction from the refueling water storage tank upon being manually realigned and automatically transferring suction to the containment sump during the recirculation phase of operation.

APPLICABILITY:

MODE 4.

ACTION:

'With no ECCS subsystem OPERABLE because of the inoperability of a.

either the centrifugal charging pump or the flow path from the refueling water storage tank, restore at least one ECCS subsystem to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . or be in COLD SHUTDOWN within the next-20 hours, b.

With no ECCS subsystem OPERABLE because of the inoperability of either the residual heat removal heat exchanger or residual heat removal pump, restore at least one ECCS subsystem to OPERABLE status.

or maintain the Reactor Coolant System T less than 350*F by use of alternate heat removal methods.

avg c.

In the event the ECCS is actuated and injects water into the Reactor Coolant System, a REPORTABLE EVENT shall be prepared and submitted to the Commission pursuant to Specification 6.6.1.

This report shall include a description of the circumstances of the actuation and the total accumulated actuation cycles to date. 'The current value of the usage factor for each affected safety injection nozzle shall be provided in this report whenever its value exceeds 0.70.

-SEQUOYAH - UNIT-1 3/4 5-9 Ar.iendment No. 36

CONTAINMENT SYSTEMS CONTAINMENT VESSEL-STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.6 The structu al integrity of the containment vessel shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.6.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With the structural integrity of the containment vessel not conforming to the above requirements, restore the structural integrity to within the limits prior to increasing the Reactor Coolant System temperature above 200 F.

SURVEILLANCE REQUIREMENTS 4.6.1.6 The structural integrity of the containment vessel shall be determined during the shutdown for each Type A containment leakage rate test (Specification 4.6.1.2) by a visual inspection of the exposed accessible interior and exterior surfaces of the vessel.

This inspection shall be performed prior to the Type A containment leakage rate test to verify no apparent changes in appearance of the surfaces or other abnormal degradation.

Any abnormal degradation of the containment vessel detected during the above required inspections shall be reported to the Commission pursuant to Specification 6.6.1.

f SEQUOYAH - UNIT 1 3/4 6-11 Amendment f:o. 36

CONTAINMENT SYSTEMS SHIELD BUILDING STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION

3. 6. J. 7 The structural integrity of'the shield building shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.7.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With-the structural integrity of the shield building not conforming to the above requirements, restore the structural integrity to within the limits prior to increasing the Reactor Coolant System temperature above 200*F.

SURVEILLANCE REQUIREMENTS 4.6.1.7 1Dua structural integrity of the shield building shall be determined during the shutdown for each Type A containment leakage rate test (reference Specification 4.6.1.2) by a visual inspection of the exposed accessible interior and exterior surfaces of the shield building and verifying no apparent changes in appearance of the concrete surfaces or other abnormal degradation.

Any abnormal degradation of the shield building detected during the above required inspections shall be reported to the Commission pursuant to Specification 6.6.1.

l 1

SEQUOYAh - UNIT 1 3/4 6-12 Amendment No. 36

1-e PLANT SYSTEMS 3/4.7.11 FIRE SUPPRESSION SYSTEMS FIRE SUPPRESSION WA'TER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.11.1 The fire suppression water system shall be OPERABLE with:

a.

Two fire suppression pumps, each with a capacity of 1174 gpm, with their discharge aligned to the fire suppression header, b.

An OPERABLE flow path capable of taking suction from the forebay and transferring the water through distribution piping with OPERABLE sectionalizing control or isola' tion valves to the yard hydrant curb valves, the last valve ahead of the water pressure alarm device on each sprinkler or hose standpipe, and the last valve ahead of the deluge valve on each deluge or spray system required to be OPERABLE per Specifications 3.7.11.2 and 3.7.11.4.

APPLICABILITY:

At all times.

ACTION:

a.

With only one pump OPERABLE, restore the inoperable equipment to OPERABLE status within 7 days or, in lieu of any other report required by Specification 6.6.1, prepare and submit a Special Report to the l

Commission pursuant to Specification 6.9.2 within the next 30 days outlining the plans and procedures to be used to restore the inoperable equipment to OPERABLE status or to provide an alternate backup pump or supply.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

b.

With the fire suppression water system otherwise inoperable:

1.

Establish a backup fire suppression water system within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and 2.

In lieu of any other report required by Specification 6.6.1, l

submit a Special Report in acccidance with Specification 6.9.'2:

a)

By telephone within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b)

Confirmed by telegraph, mailgram or facsimile transmission no later than the first working day following the event, and SI: CtAH - UNIT 1 3/4 7-31 Amendwnt Nm %-

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PLANT SYSTEMS SPRAY AND/0R SPRINKLER SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.41.2 'The following spray and/or' sprinkler systems shall be OPERABLE:

a.

Reactor Building - RC pump area, Annulus b.

Auxiliary Building - Elev. 669, 690, 706, 714, 734, 749, 759, ABGTS Filters, EGTS Filters, Cont. Purge Filters,

~

and 125V Battery Rooms.

c.

Control Building -

Elev. 669, Cable Spreading Room, MCR air filters, and operator living area.

d.

Diesel Generator Building - Corrider Area.

e.

Turbine Building - Control Building Wall.

APPLICABILITY:

Whenever equipment protected by the sp. ray / sprinkler system is required to be OPERABLE.

ACTION:

a.

With one or more of the above required spray and/or sprinkler systems inoperable, within one hour establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant systems or components could be damaged; for other areas establish an hourly fire watch patrol.

Restore the system to OPERABLE status within 14 days or, in lieu of any other report required by Specifica-tion G.6.1, prepare and submit a Special Report to the Commission l

pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

b.

The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7'.11.2 Each of the above required spray and/or sprinkler systems 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 is in its correct position.

At least once per 12 months by cycling each testable valve in tIhe b.

flow path through at least one complete cycle of full travel.

5E?UOV/.H - UNIT -1 3/4 7-33 Amendment No. 36

o PLANT SYSTEMS C

SYSTEMS 2

LIMITING CONDITION FOR OPERATION 3.7.11.3 The follow.ing low pressure CO systems shall be OPERABLE.

2 a.

Computer Room.

b.

Auxiliary Instrument Room.

c.

Diesel Generator Rooms.

d.

Fuel Oil Pump Rooms.

systems is required to APPLICABILITY: Whenever equipment protected by the CO2 be OPERABLE.

ACTION:

a.

With one or more of the above required CO systems inoperable, 2

within one hour establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant systems or components could be damaged; for other areas, citablish an hourly fire watch patrol.

Restore the system to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.6.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and sch'edule for, restoring the system to OPERABLE status, b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.11.3.1 Each of the.above requir'ed CO systems shall be demonstrated 2

OPERABLE at least once per 31 days by verifying that each valve (manual, power

~

operated or automatic) in the flow path is in its correct position.

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ii?)OYAll - UNIT 1 3/4 7-35 Amendment No. 36

PLANT SYSTEMS

~ FIRE H0SE STATIONS LIMITING CONDITION FOR OPERATION 3.7.11.4.The fire hose stations shown in Table 3.7-10 shall be OPERABLE.

APPLICABILITY: Whenever equipment'in the areas protected by the fire hose stations is required to be OPERABLE.

ACTION:

i a.

With one.or more of the fire hose stations shown in Table 3.7-10 inoperable, route an additional equivalent capacity fire hose to the unprotected area (s) from an OPERABLE hose station within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months if the inoperable fire hose is the primary means of fire suppression; otherwise route the additional hose within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .. Restore the fire hose station to OPERABLE status within 14 days or, in lieu of any other report required by Specification G.6.1, prepare and submit a Special-Report to-the Commission pursuant to Specification 6.9.2 wjthin the next 30 days outlining the action taken, the cause of the inoperability, and the plans and schedule for restoring the station to OPERABLE status.

_The provisions'of Specifications 3.0.3 and 3.0.4 are not applicable.

b.

SURVEILLANCE REQUIREMENTS i

4.7.11.4 Each of the fire hose stations sh'own in Table 3.7-10 shall be demonstrated OPERABLE:

i a.

At least once per 31 days by visual inspection of the stations accessible during plant operations to assure all required equipment is at the station.

b.

At least once per 18 months by:

1.

Visual inspection of the stations not accessible during plant operations to assure all required equipment is at the station, 2.

Removing the hose for inspection and re-racking, and i

I 3.

Inspecting all gaskets and replacing any degraded gaskets in the couplings.

c.

At least once per 3 years by:

1 1.

Partially opening each hose station valve to verify valve-OPERABILITY and no flow blockage.

2.

Conducting a hose hydrostatic test at a pressur_e of 150 psig or at least 50 psig above maximum fire main operating pressure, whichever is greater.

SEQU0iAH - UNIT l' 3/4 7-37

- Amendment No. 36'

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l PLANT SYSTEMS 3/4.7.12 FIRE BARRIER PENETRATIONS LIMITING CONDITION FOR OPERATION 3.7.12 All fire barrier penetrations (including cable penetration barriers, firedoors and fire dampers) in fire zone boundaries protecting safety related areas shall be functional.

A)PLICABILITY:

At all times.

ACTION:

a.

With one or more of the above required fire barrier penetrations non-functional, within one hour either, establish a continuous fire watch on at least one side of the affected penetration, or verify the OPERABILITY of fire detectors on at least ene side of the non-functional fire barrier and establish a hourly fire watch patrol.

Restore the non-functional fire barrier penetration (s) to functional status within 7 days or, in lieu of any other report required by Specification 6.6.1, prepare and submit a Special Report to the l

Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the non-functional pene-tration and plans and schedule for restoring the fire barrier penetration (s) to functional status, b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.12 Each of the above required fire barrier penetrations shall be verified' to be functional:

'a.

At least once per 18 months by a visual inspection b.

Prior to returning a fire barrier penetration to functional status following repairs or maintenance by performance of a visual inspec-tion of the affected fire barrier penetration (s).

i SLO!K 'AH - UNIT 1 3/4 7-41 Amendment No. 36

F

' RADI0 ACTIVE EFFLUENTS DOSE LIMITING' CONDITION FOR OPERATION i

3.11.1.2 The dose or dose commitment to an individual from radioactive materials in liquid effluents released from the site (see Figure 5.1-1) shall be limited to the following*:

a.

During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and b.

During any calendar year to less than or equal to 3 mrem to the total body and to less' than or equal to 10 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

a.

With the calculated dose from the release of' radioactive materials in liquid effluents exceeding any of the above limits, in lieu of

..any other report required by Specification 6.6.1, prepare and submit

.l to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters, so that the cumulative dose or dose commitment to an individual from these releases is within 3 mrem to the total i

body and 10 mrem to any organ.

This Special Report shall also include (1) the results of radiological analyses of the drinking water source and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR 141, Safe Drinking Water Act.

b.

The provisions of specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.2 Dose Calculations.

Cumulative dose contributions from liquid effluents shall be determined in accordance with the ODCM at least once per 31 days.

^Per reactor unit SEQ L Ji - U*:IT 1 3/4 11-5 An:enument No. 36

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RADI0 ACTIVE EFFLUENTS LIQUID WASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.1.3 The liquid radwaste treatment system shall be OPERABLE.

The appro-priate portions of the system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent from the site (see Figure 5.1-1) when averaged over 31 days, would exceed 0.06 mrem to the total body or 0.2 mrem to any organ *,

APPLICABILITY:

At all times.

ACTION:

a.

With the liquid radwaste treatment system inoperable for more than 31 days or with radioactive liquid waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by Specification 6.6.1, prepare and submit to the l

Commission within 30 days pursuant to Specification 6.9.2 a Special Report which includes the following information:

1.

Identification of the inoperable equipment or subsystems and the reason for inoperability, 2.

Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3.

Summary description of action (s) taken to prevent a recurrence.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.'

SURVEILLANCE REQUIREMENTS 4.II.1.3.1 Doses due to liquid releases shall be projected at least once per 31 days, in accordance with the ODCM.

4.11.1.3.2 The liquid radwaste treatment system shall be demonstrated OPERABLE by operating the liquid. radwaste treatment system equipment for at least 15 minutes at least once per'92 days unless the liquid radwaste system has been utilized to process radioactive liquid effluents during the previous 92 days.

J 1

^P(r reactor unit SI"J. RAH - UMIT 1 3/4 11-6 Amendment No. 36

o RADI0 ACTIVE EFFLUENTS DOSE - NOBLE GASES LP'ITING CONDITION FOR OPERATION 3.11.2.2 The air dose due to noble gases released in gaseous effluents from the site (see Figure 5.1-1) shall be limited to the following*:

a.

During any calendar quarter:

Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and, b.

During any calendar year:

Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

APPLICABILITY:

At all times.

ACTION a.

With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits,_in lieu of any other report required by Specification 6.6.1, prepare and submit to the l

._ Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases of radioactive noble gases in gaseous effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters, so that the cumulative dose is within 10 mrad for gamma radiation and 20 mrad for beta radiation.

.b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 1

4.11.2.2 Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with the ODCM at least once per 31 days.

Per reactor unit.

i SEQUO:LH - UNIT 1 3/4 11-12 Amendment No. 36

a RADIOACTIVE EFFLUENTS DOSE - RADI0 IODINES, RADIOACTIVE MATERIALS IN PARTICULATE FORM, AND RADIONUCLIDES OTHER THAN NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to an individual from radiciodines and radioactive materials in particulate form, and radionuclides (other than noble gases) with half-lives greater than 8 days in gaseous effluents released from the site (see Figure 5.1-1) shall be limited to the following*:

a.

During any calendar quarter:

Less than or equal to 7.5 mrem to any organ and, b.

During any calendar year:

Less than or equal to 15 mrem to any organ.

APPLICABILITY:

At all times.

~

ACTION:

a.

With the calculated dose from the release of radiciodines, radioactive materials in particulate form, or radionuclides (other than noble gases) with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, in lieu of any other report required by Specification 6.6.1, prepare and submit to tne Commission l

2 within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions to be taken to reduce the releases of radio-

~

i iodines-and radioactive materials in particulate form, and radio-nuclides (other than nobles gases) with half-lives greater than 8 days in gaseous effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters, so that the cumulative dose or dose commitment to an individual from these releases is within 15 mrem to any organ.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.3 Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance l

with the ODCM at least once per 31 days.

l

^Fer reactor unit.

SEQUG(AH - UNIT _1 3/4 H-13 Amendment No. 36

RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT e

LIMITING CONDITION FOR OPERATION 3.11.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE.

The appropriate portions of the GASEOUS RADWASTE TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases from the site (see Figure 5.1-1), when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad

~

for beta radiation *.

The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce. radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases from the site (see Figure 5.1-1) when averaged over 31 days would exceed 0.3 mrem to any organ.*

APPLICABILITY:

At all times.

ACTION:

a.

With the GASE0US RADWASTE TREATMENT SYSTEM and/or the VENTILATION

._ EXHAUST TREATMENT SYSTEM inoperable for more than 31 days or with gaseous waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by Specifica-tion 6.6.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which includes the following information:

1.

Identification of the inoperable equipment or subsystems and the reason for inoperability, 2.

Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3.

Summary description of action (s) taken to prevent a recurrence.

b.

The provisions.of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with the ODCM.

4.11.2.4.2 The GASEOUS RADWASTE TREATMENT SYSTEM and VENTILATION EXHAUST TREAT-MENT SYSTEM shall be demonstrated OPERABLE by operating the GASEOUS RADWASTE I

TREATMENT SYSTEM equipment and VENTILATION EXHAUST TREATMENT SYSTEM equipment l

for at least 15 minutes, at least once per 92 days unless the appropriate system l

has been utilized to process radioactive gaseous effluents during the previous l

92 days.

^1hese crses are per reactor unit.

j SEQUDYAH - UNIT 1 3/4 11-14

' Amendment No. 36 I

-o RADIOACTIVE EFFLUENTS s

3/4.11.3 SOLID RADIOACTIVE WASTE LIMITING CONDITION FOR OPERATION

+

i 3.11.3 The solid radwaste system.shall be OPERABLE and used, as applicable in 4

accordance with a PROCESS CONTROL PROGRAM, for the SOLIDIFICATION and packaging of radioactive wastes to. ensure' meeting the requirements of 10 CFR Part 20 and of 10 CFR Part 71 prior to shipment of radioactive-wastes from the site.

~

APPLICABILITY: At all times.

ACTION:

a.

With the packaging. requirements of 10 CFR'Part 20 and/or 10 CFR Part 71 not satisfied, suspend shipments of defectively packaged solid radioactive wastes from the site.

b.

With the solid radwaste system inoperable for more than 31 days, in lieu of any other report required by Specification 6.6.1, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.2 a Special Report which includes the following information:

1.

Identification of the inoperable equipment or subsystems and the reason for inoperability, 2.

Action (s) taken to restore the inoperable equipment to OPERABLE status, i

3.

A description of the alternative used for SOLIDIFICATION and

^

packaging of radioactive wastes, and 4.

Summary description of action (s) taken to prevent'a recurrence.

'c The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

1 SURVEILLANCE REQUIREMENTS

~

l 4.11.3.1 The solid radwaste system shall be demonstrated OPERABLE at least once per 92 d ys by:

a.

Operating the solid radwaste system at least once in the previous 92 days in accordance with the PROCESS CONTROL PROGRAM, or l

b.

Verification of the existence of a valid contract for. SOLIDIFICATION 4

i to be performed by a contractor in accordance with a PROCESS CONTROL PROGRAM.

.a.:uGYAH - UNIT 1

-3/4 11-17 Amendment No.36 5

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RADI0 ACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE LIMITING CONDITION FOR OPERATION 3.11.4 The dose or dose commitment to any member of the public, due to releases of. radioactivity from uranium fuel cycle sources, shall be limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrem) over 12 consecutive months.

APPLICABILITY:

At all times.

ACTION:

a.

With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifica-ti ons 3.11.1. 2. a, 3.11.1. 2. b, 3.11. 2. 2. a, 3. l l. 2. 2. b, 3. l l. 2. 3. a or 3.ll.2.3.b, in lieu of any other report required by Specification 6.6.1, prepare and submit a Special Report to the D.irector, Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, D.C.

20555, within 30 days, which defines the corrective action to be taken

. to reduce subsequent releases to prevent recurrence of exceeding the limits of Specification 3.11.4.

This Special Report shall include an analysis which estimates the radiation exposure (dose) to a member of the public from uranium fuel cycle sources (including all effluent pathways and direct radiation) for a 12 consecutive month period that includes the release (s) covered by this report.

If the estimated dose (s) exceeds the limits of Specification 3.11.4, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40.CFR 190 and including the specified information of 6 190.11(b).

Submittal of the report is considered a timely request, and a variance is granted until staff' action on the request is complete.

The variance only relates to the limits of 40 CFR 190, and does not apply in any way to the requirements for dose limitation of 10 CFR Part 20, as addressed in other sections of this technical specification.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.4 Dose Calculations Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Specifications 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the ODCM.

SE(UOndi - UNIT 1 3/4 11-19 Amendment No.36

~

3/4.12 -RADIOLOGI' CAL ENVIRONMENTAL. MONITORING-3/4.12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1 'The radiological environmental,-monitoring program shall be conducted as sWcified in Table 3.12-1.

APPLICABILITY:

At all times.

ACTION:

With-the radiological. environmental monitoring program not being a.

conducted as specified in Table 3.12-1, in lieu of any other report required by Specification 6.9.1 or 6.6.2, prepare and submit to the l

Commission, in the Annual Radiological Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b.

With the level of radioactivity in an environmental sampling medium ex'ceeding the reporting levels of Table 3.12-2 when averaged over any calendar quarter, in lieu of any other report required by Specification 6.9.1 or 6.6.1, prepare and submit

to the Commission within 30 days from the end of the affected calendar quarter a Report

. pursuant to Specificiation 6.9.1.13.

When more than one of the radio-nuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitted if:

concentration (1), concentration (2) + * * 'J 1.0 limit level (1) limit level (2)

When radionuclides other than those in Table 3.12-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to an individual is equal to or greater than the calendar year limits of Specifications 3.11.1.2, 3,11.2.2 and 3.11.2.3.

This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

c.

With milk or fresh leafy vegetable samples unavailable from'one or more of the sample locations required by Table 3.12-1, in lieu of 4

any other report required by Specification 6.9.1 or 6.6.1, prepare and submit to the Commission within 30 days, pursua.nt to Specification 6.9.2, a Special Report which identifies the cause of the unpvail-ability of samples and identifies locations for obtaining replacement samples.

The locations from which samples were unavailable may then be deleted from those required by Table 3.12-1, provided the locations from which the. replacement samples were obtained are added to the environmental monitoring program as rdplacement locations.

d.

The provisions of Specifications 3.0.'3 and 3.0.4 are not applicable.

^A spC ial, report pursuant to Specification 6.9.2.

SEQ 10YAH - tm!T 1 3/4 12-1 Amendment No. '36

_ _j

l RADIOLOGICAL ENVIRONMENTAL MONITORING

~

3/4.12.2 LAND USE CENSUS

' LIMITING CONDITION FOR OPERATION j.

3.12.2. A-land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence and the nearest garden

of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sei: tors within a distance of five miles.

(For elevated releases as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use census shall also identify the locations of all milk animals and all gardens of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of three miles.)

MP,LICABILITY:

At all times.

~

ACTION:

a.

With a land use census identifying a location (s) which yields a calculated dose or dose commitment greater than the maximum values currently being calculated in Specification 4.11.2.3.1, in lieu of any other report required by Specification 6.6.1., prepare and submit

{-

to the Commission within 30 days after the updated calculation, pursuant to Specification 6.9.2, a Special Report which identifies the new location (s).

b.

With a land use census identifying a location (s) which yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than the highest calculated dose or dose commit-ment at a location from.which samples are currently being obtained in 1

accordance with. Specification 3.12.1, in lieu of any other report required by Specification 6.6.1, prepare and submit to the Commission within 30 days after the updated calculation, pursuant to Specification 6.9.2, a Special Report which identifies the new location. The new location shall be added to the radiological environmental monitoring program within 30 days, if the owner consents.

The sampling location, excluding the control station location, having the lowest calculated dose or dose commitment (via the same exposure pathway) may be deleted from this -

)

monitoring program after October 31 of the year in which this land use census was conducted.

i

.c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

l

, SURVEILLANCE REQUIREMENTS J

l 4.12.2 The land use census shall be conducted at least once per calendar year 1

between the dates of April 1 and Octo.ber 1 using the following-techniques:

l.

1.

Within a 2-mile radius from the plant or within the 15-mrem / year isodose i

line, whichever is larger, enumeration by a door-to-door or. equivalent

~

counting technique.

-2.

Within a-5-mile radius from the plant, enumeration by using appropriate techniques.such as door-to-door survey, mail survey, telephone survey, aerial survey, or information from local agricultural authorities or other rel.iable sources.

^ Broad leaf vegetation sa'::pling may be perfor'med at the site boundary in the L

_ direction sector.with'the highest D/Q in lieu c( the garden census.

SEQUOYAH - UfIT 1 3/4 12-10 Amendment No. 36 l

_.. _. ~ _.

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ADMINISTRATIVE CONTROLS l

- d.

Review of proposed changes to the Technical. Specifications.related J.-

.to' radiological assessments involving dose calculations and projections l

and environmental monitoring.

Authority

- 6.5.J.7 The RARC shall:

F a.

Recommend in writing to the Chief, Radiological Hygiene Branch f

approval or disapproval of items considered under 6.5.3.6 above.

b.

Render determinations-in writing with regard to whether or not each item considered under 6.5.3.6 constitutes an unreviewed safety 6

question.

c.

Provide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Director, Nuclear Power Division and the Nuclear Safety Review Board of disagreement between the RARC and the Chief, Radiological Hygiene Branch; however, the Chief, Radiological Hygiene Branch shall have responsibility for resolution of-such disagreement pursuant to 6.1.2~above.

I Records i

6.5.3.8_

The RARC shall maintain ~ written minutes of each RARC meeting that at a minimum.. document the results of all RARC activities performed under the responsibility and authority provisions of these technical specifications.

Copies shall be provided to the Director, Nuclear Power Division, PORC, and the Nuclear Safety Review Board.

6.6 REPORTABLE EVENT ACTIGN i

6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a.

The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50i and b.

Each REPORTABLE EVENT shall be reviewed by the PORC and the results of this review shall be submitted to the NSRB and the Director, Nuclear Power Division.

6.7 SAFETY LIMIT VIOLATION.

l 6.7.1 The~following actions shall be taken in the event a Safety' Limit is-violated:

i

~

- a.

The unit shall be placed in at least HOT STANDBY within one hour.

b.

The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour.

The Director,' Nuclear Power Division'and the NSRB shall be notified with 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

9 i

SEQUOYAH - talif1 6-14 Amendment Ho. 36 i

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ADMINISTRATIVE CONTROLS 6.9 REPORTING REQUIREMENTS 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 to the Director of the Regional Office of Inspection and Enforcement unless otherwise noted.

STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications.

Any corrective actions that were required to obtain satisfactory operation shall. also be described.

Any additional specific details required in license conditions based on other commitments shall be included in this report.

6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.

If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

SEQUOYAH - UNIT 1 6-16 Amendment No. 36

ADMINISTRATIVE CONTROLS The radioactive effluent release report to be submitted 60 days after January 1

.of each year shall also include an assessment of radiation doses to the likely most exposed members of the public from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous 12 consecutive months to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation.

Acceptable methods'for calculating the dose' contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1.

The radioactive effluent release reports shall include the following information for each type of solid waste shipped offsite during the report period:

a.

Container volume,

~

b.

Total curie quantity (specify whether determined by measurement er estimate),

c.

Principal radionuclides (specify whether determined by measurement or estimate),

d.

Type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms),

e.

Type of container (e.g., LSA, Type A, Type 8, Large Quantity), and f.

SOLIDIFICATION agent (e.g., cement, urea formaldehyde).

The radioactive effluent release reports shall include unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents on a quarterly basis.

The radioactive effluent release reports shall include any changes to the PROCESS CONTROL PROGRAM (PCP) made during the reporting period.

MONTHLY REACTOR OPERAITNG REPORT 6.9.1.10 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or Safety Valves, shall be submitted on a monthly basis to the Director, Office of Management and Program Analysis, U.S. Nuclear Regulatory Commission, Washington, D.C.

20555, with a copy to the Regional Office of Inspection and Enforcement, no 1ater

~

than the 15th of each month following the calendar month covered by the report.

Any changes to the OFFSITE DOSE CALCULATION MANUAL shall be submitted with the Monthly Operating Report within 90 days in which the change (s) was made effective.

In addition, a report of any major changes to the radioactive waste treatment systems shall be submitted with the Monthly Operating Report for the period.in which the evaluation was reviewed and accepted by the PORC.

SEQUOYAH - UMIT 1 6-19 Amendment No. 36

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f 6-20 Amendment tio. 36 SEC JCYA!i - 01:11 1 3

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THIS PAGE DELETED i

SECUOYAli - tr.IT 1 6-21 Amendment No. 36 i

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ADMINISTRATIVE CONTROLS

+

RADIAL PEAKING FACTOR LIMIT REPORT 6.9.1.14 The W(z) function for normal op'eration shall be provided to the Direc '

tor, Nuclear Reactor Regulation, Attention, Chief of the Core Performance Branch, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555 at least 60 days prior to cycle initial criticality.

In the event that these values would be submitted at some other time during core life, it will;be submitted 60 days prior to the date the values would become effective unles's otherwise exempted by the_ Commission.

.i' Any information needed to suport W(z) will be by request from the NRC and need not be included in this report.

SPECIAL REPORTS 6.9.2 Special reports shall be' submitted to the Director of the Office of Inspection and Enforcement Regional _0ffice_within the time period specified for each report.

6.10 RECORD RETENTION In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

6.10.1 The following records shall be retained for at least five years:

a.

Records and logs cf unit operation covering time interval at each power level.

b.

Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.

1 c.

All REPORTABLE EVENTS submitted to the Commission.

d.

Records of surveillance activities, inspections and calibrations required by these Tech.7ical Specifications.

Records of changes made to the procedures required by Soecification e.

6.8.1 and 6.8.4.

f.

Records of radioactive shipmentd.

g.

Records of sealed source and fission detector leak tests and results.

h.

Records of annual physical inventory of all sealed source matgrial of record.

t t

SfQUDYt.H - U"IT 1 6-22 Amendment No. 36 i

REACTOR COOLANT SYSTEM BASES The plant is expected to be operated in a manner such that the. secondary coolant will be maintained within those chemistry limits found to result ii negligible corrosion of the steam generator tubes.

If the secondary coolant cheristry is not maintained within these limits, localized corrosion may likely result in stress corrosion cracking.

The extent of cracking during plant operation would be limited by the limitation of. steam generator tube leakage between the primary coolant system and the secondary coolant system (primary-to-secondary leakage = 500 gallons per day per steam generator).

Cracks having a primary-to-secondary leakage less than this limit during operation will have an adequate margin of safety to withstand the loads imposed during normal operation and by postulated accidents.

Operating plants have demonstrated that primary-to-secondary leakage of 500 gallons per day per steam generator can readily be detected by radiation monitors of steam generator blowdown.

Leakage in excess of this limit will require plant shutdown and an unscheduled inspection, during which the leaking tubes will be located and plugged.

Wastage-type defects are unlikely with proper chemistry treatment of the secondary coolant.

However, even if a defect should develop in service, it will be found during scheduled inservice steam generator tube examinations.

Plugging will be required for all tubes with imperfections exceeding the plugging. limit of 40% of the tube nominal wall thickness.

Steam generator tube inspections of operating plants have demonstrated the capability to reliably detect degradation that has penetrated 20% of the original tube wall thickness.

Whenever the results of any steam generator tubing inservice inspection fall into Category C-3, these results will be promptly reported to the Commission pursuant to Specification 6.6.1 prior to resumption of plant opera-tion.

Such cases will be considered by the Commission on a case-by-case basis and may result in a requirement for analysis, laboratory examinations, tests, additional eddy-current inspection, and revision of the Technical, Specifications, if necessary.

3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.6.1 LEAKAGE DETECTION SYSTEMS The RCS leakage detection systems required by this specification are provided to monitor and detect leakage from the Reactor Coolant Pressure Boundary.

The'se detection systems are consistent with the recommendations of Regulatory Guide 1.45, " Reactor Coolant Pressure Boundary Leakage Detection Systems," May 1973.

.I SEQtiot;H - UNIT 1 B 3/4 4-3 Amendment No. 36 m_.,

CONTAINMENT SYSTEMS AIR TEMPERATURE LIMITING CONDITION FOR OPERATION

3. 6.1. 5 Primary con.tainment average air temperature shall be maintained:

a.

between 85*F* and 105*F in the containment upper compartment, and b.

between 100*F* and 125*F in the containment lower compartment.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With the containment average air temperature not conforming to the above limits, restore the air temperature to within the limits within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 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 .

SURVEII. LANCE REQUIREMENTS 4.6.1.5.1 The primary containment upper compartment average air temperature shall be the weighted average ** of all ambient air temperature monitoring stations located in the upper compartment.

As a minimum, temperature readings will be obtained at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from the following locations:

Location a.

Elev. 743 ft, b.

Elev. 786 ft.

c.

Elev. 786 or 845 ft.

4.6.1.5.2 The primary containment lower compartment average air temperature shall be the weighted average ** of all ambient air temperature monitoring stations located in the lower compartment.

As a minimum, temperature readings will be obtained at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from the following locations:

Lucecion a.

Elev. 722 ft.

b.

Elev. 700 ft.

c.

Elev. 685 or 703 ft.

Lower limit may be reduced to 60 F in MODES 2, 3 and 4.

^^ The weighted average is the sum of each temperature multiplied by its respective containment volume fraction.

In the event of inoperable temperature sensor (s), the weighted average shall be taken as the reduced totai divid'ed by one minus the volume fraction represented by the sensor (s) out of service.

Si:0.0 /U. - UNIT 1 3/4 6-10 Amendment No. 36 d

PLAh4TSYSTEMS ACTION:

(Continued) c)

In writing within 14 days following the event, outlinirg the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

SURVEILLANCE REQUIREMENTS 4.7.11.1 The fire suppression water system shall be demonstrated OPERABLE:

a.

At least once per 31 days on a STAGGERED TEST BASIS by starting each

~~

electric motor driven pump and operating it for at least 15 minutes on recirculation flow.

b.

At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path is in its correct position.

c.

At least once per 6 months by performance of a system flush.

d.

A't least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel.

e.

At least once per 18 months by performing a system functional test

-avhich includes simulated automatic actuation of the system throughout its operating sequence, and:

l.

Verifying that each automatic valve in the flow path actuates to its correct position,.

2.

Verifying that each pump develops at least 1174 gpm at a system head of 312 feet, 3.

Cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel, and 4.

Verifying that the No.1 fire pump starts to maintain the fire suppression water system pressure greater than or equal to 125 psig and that the No. 2 fire pump also starts automatically within 10 + 2 seconds when the fire suppression water syste.n is not maintained greater than or equal to 125 psig by the No. 1 pump.

f.

At least once per 3 years by performing a flow test of the system in accordance with Chapter 5, Section 11 of the Fire Protection Handbook, 14th Edition, published by the National Fire Protection Association.

4

^ Note:

These flushes should coincide with the chlorination of the raw service and fire suppression water system.

These flushes should be run, one between April 1 and June 30, and the other between

. September 1 and November 15.

Within the prescribed spring and fall test period, deviation from the six-month performance frequency is authorized.

SE;UOYAH - UNIT 1 3/4 7-32 Amendment No. 13 y

y

~

,d o

UNITED STATES y

f;* g NUCLEAR REGULATORY COMMISSION g-

.. x, y WASHINGTON, D. C. 20555

%,4.,,,.:~ *.{ f TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEOUOYAH NUCLEAR PLANT, UNIT 2

. AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 28 License No. DRP-79 1.

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

A.

The applications for amendment.to the Sequoyah Nuclear Plant, Unit 2 (the facility) Facility Operating License No. DPR-79 filed by the Tennessee Valley Authority (licensee), dated July 21, 1983, December 29, 1983, and April 20, 1984, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the license, as amended, the provisions of the Act, and the rules and regulations of the Com-mission; 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 Comission'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 Comission's regulations and all applicable requirements have been satisfied.

P.

Accordingly, the license is hereby amended by page changes to the Appendix A Technical Specifications as indicated in the attachment to this license amend-ment, ard paragraph 2.C.(2) of Facility Operating License No. DPR-79 is hercby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 28, are hereby incorporated into the license.

-2 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

& t.?

(',ihnsn~--

n Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing

Attachment:

Appendix A Technical Specification Changes Date of Issuance: November 23, 1984

W 6

4 i

O L

h

ATTACHMENT TO LICENSE AMENDMENT ~NO. 28 FACILITY OPERATING LICENSE NO. DPR-79 DOCKET NO. 50-328 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.

Amended Page 3/4' 4-32 5-6 3/4 8-17 1-5 3/4 1-4 3/4 3-59 3/4 4-14 3/4 4-16 3/4 4-25 3/4 5-5 3/4 5-9 3/4 6-11 3/4 6-12 3/4 7-43 3/4 7-45 3/4 7-47 3/4 7-48 3/4 7-52 3/4 11-5 3/4 11-6 3/4 11-12 3/4 11-13 3/4 11-14 3/4 11-17 3/4 11-19 3/4 12-1 3/4 12-10 6-17 6-21 6-24 6-25 6-26 6-27 6-28 i

~

REACTOR COOLANT SYSTEM PRESSURIZER LIMIT;NGCONDITIONFOROPERATION 3.4.2.2-The pressurizer temperature'shall be limited to:

a.

A maximum heatup of 100*F in any one hour period, b.

A maximum cooldown of 200*F in any one hour period, and c.

A maximum spray water temperature differential of 560*F.

~

APPLICABILITY:

At all times.

ACTION:

With the pressurizer temperature limits in excess of any of.the above limits, restore the temperature to within the limits within 30 minutes; perform an engineering evaluation to determine the effects of the out-of-limit condition on the structural integrity of the pressurizer; determ,ine that the pressurizer remains acceptable for continued operation 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 reduce the pressurizer pressure to less than 500 psig with-in the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.4.9.2.1 The pressurizer temperatures shall be determined to be within the limits at least once per 30 minutes during system heatup or cooldown.

4.4.9.2.2 Any occurrence of spray operation with a differential temperature greater than 320*F shall be recorded for evaluation of the cyclic limits in Table 5.7.1.

4 9

SECUL n-Ut:IT 2 3/4 4-32 Amendo.ent !!o. 28

~

.-...-y.

TABLE 5.7-1 N

COMPONENT CYCLIC OP. TRANSIENT LIMITS y

c CYCLIC OR DESIGN CYCLE COMPONENT TRANSIENT LIMIT OR TRANSIENT c

Ii

.Reaciar Coolant System 200 heatup cycles at < 100*F/hr Heatup cycle - T from < 200*F and 200 cooldown cycles at to > 550*F.

- 9

< 100*F/hr.

Cooldown. cycle - T avg.from

> 550 F to 5 200*F.

200 pressurizer cooldown cycles Pressurizer cooldown cycle at 1 200 F/hr.

temperatures from > 650*F.to 5 200 F.

80 loss of load cycles, without

> 15% of RATED THERMAL POWER to S'

immediate turbine or reactor trip.

0% of RATED THERMAL POWER.

m 1

40 cycles of loss of offsite Loss of offsite A.C. electrical A.C. elrctrical power.

power source supplying the onsite ESF' Electrical System.

80 cycles of loss of flow in one Loss of only one reactor reactor coolant loop.

coolant pump.

400 reactor trip cycles.

100% to 0% of RATED THERMAL POWER.

12 spray actuation cycles.

Spray water temperature differential

> 320*F and 5 560*F.

IT 50 leak tests.

Pressurized to 2485 psig.

!}';

5 hydrostatic pressure tests.

Pressurized to 3105 psig.

p

]

Secondary System 5 hydrostatic pressure tests.

Pressurized to 1330 psig.

1 0

.o ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

(c) For each circuit breaker found inoperable during these functional tests, an additional representative sample of at least 1 of the curcuit breakers of the inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested.

2.

By selecting and functionally testing a representative sample of at least 10% of each type of lower voltage circuit breakers.

Circuit breakers selected for functional testing shall be selected on a rotating basis.

For the lower voltage circuit breakers the nominal trip setpoint and short-circuit response time are listed in Table 3.8-1.

Testing of these circuit breakers will consist of injecting a current in excess of the breakers nominal setpoint and measuring the response time.

The measured response time will be compared to the manufacturer's data to ensure that it is less than or equal to a value specified by the manufacturer.

Circuit breakers found inoperable during functional testing shall be restored to OPERABLE status prior to resuming operation.

For each circuit breaker found inoperable during these functional tests, an additional representative sample of at least 10% of all the circuit breakers of the inoperable type shall also be

. functionally tested until no more failures are found or all circuit

~ breakers of that type have been functionally tested.

3.

By selecting and functionally testing a representative sample of each type of fuse on a rotating basis.

Each representative sample of fuses shall include at least 10% of all fuses of that type.

The functional test shall consist of a non-destructive resistance measure-ment test which demonstrates that the fuse meets its manufacturer's design criteria.

Fuses found inoperable during these functional tests shall be replaced with OPERABLE fuses prior to resuming operation.

For each fuse found inoperable during these functional tests, an additional representative sample of at least 10%'of all fuses of that type shall be functionally tested until no more failures are found or all fuses of that type have been functionally tested.*

b.

At least once per 60 months by subjecting each circuit breaker to an inspection and preventive maintenance in accordance with procedures prepared in conjunction with its manufacturer's recommendations.

Surveillance' requirement 4.8.3.1.a.3 may be suspended until the completion of the NRC generic study, provided the following surveillance requirement is l

implemented:

A fuse inspection and maintenance program will be maintained to ensure that:

1.

the proper size and type of fuse is l'nstalled, 2.

the fuse shows no sign of deterioration, and 3.

the fuse connections are tight and clean.

SECUMAh - UNIT 2' 3/4 8-17 Amonnment No. 28

-o

'0EFINITIONS PURGE - PURGING 1.21 PURGE or PURGING is the centro 11ed process of discharging air or gas

.from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify tte confinement.

OUADRANT POWER TILT RATIO 1.22 QUADRANT POWER TILT RATIO shall be the ratio of the maximum upper excore detector calibrated output to the average of the upper excore detector cali-brated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, which-ever is greater. With one excore detector inoperable, the remaining three detectors shall be used for computing the average.

RATED THERMAL POWER 1.23 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3411 MWt.

REACTOR TRIP SYSTEM RESPONSE TIME 1.24 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until loss of stationary gripper coil voltage.

REPORTABLE EVENT 1.25 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.

SHIELD BUILDING INTEGRITY 1.26 SHIELD BUILDING INTEGRITY shall exist when:

a.

The door in each access opening is closed except when the access opening is being used for normal transit entry and exit, b.

The emergency g'as treatment system is OPERABLE.

c.

The sealing mechanism associated with each penetration (e.g., welds, bellows or 0-rings) is OPERABLE.

L_MW H - UNIT 2 1-5 Amendraut No. 28

REACTIVITY CONTROL SYSTEMS MODERATOR TEMPERATURE COEFFICIENT LIMITING CONDITION FOR OPERATION 3.1.i.3 The moderator temperature coefficient (MTC) shall be:

a.

Less positive than 0 delta k/n/*F for the all rods withdrawn, beginning of cycle life (80L), hot zero THERMAL POWER condition.

b.

Less negative than -4 x 10'4 delta k/k/*F for the all rods withdrawn, end of cycle life (EOL), RATED THERMAL POWER condition.

APPLICABILITY:

Specification 3.1.1.3.a - MODES 1 and 2* only#

Specification 3.1.1.3.b - MODES 1, 2 and 3 only#

ACTION:

a.

With the MTC more positive than the limit of 3.1.1.3.a above, operation in MODES 1 and 2 may proceed provided:

1.

Control rod withdrawal ifmits are established and maintained sufficient to restore the MTC to less positive than 0 delta k/k/'F within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

These withdrawal limits shall be in addition to the insertion limits of Specification 3.1.3.6.

2.

The control rods are maintained within the withdrawal limits established above until a subsequent calculation verifies that the MTC has been restored to within its limit for the all rods withdrawn condition.

3.

In lieu of any other report required by Specification 6.6.1, a l

Special Report is prepared and submitted to the Commission pursuant to Specification 6.9.2 within 10 days, describing the value of the measured MTC, the interim control rod withdrawal limits and the predicted average core burnup necessary for restoring the positive MTC to within its limit for the all rods withdrawn condition.

b.

With the MTC more negative than the limit of 3.1.1.3.b above, be in HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

"With K,ff greater than or equal to 1.0

See S'pecial Test Exception 3.10.3 SEQUC 4 - L"!!T 2 3/4 1-4 Amendm nt No.28

INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 3.3-11 shall be OPERABLE.

APPLICABILITY:

Whenever equipment protected by the fire detection instrument is required to be OPERABLE.#

ACTION:

With the number of OPERABLE fire detection instrument (s) less than the minimum

~

number OPERABLE requirement of Table 3.3-11:

a.

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour, unless the instrument (s) is located in:;ide the containment, then inspect the containment at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or monitor the containment air temperature at least once per hour at the locations listed in Specification 4.6.1.5.

b.

Restore the inoperable instrument (s) to OPERABLE status within 14 days or, in lieu of any other report required by Specifica-tion 6.6.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the instrument (s) to OPERABLE status.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.8.1 Each of the above required fire detection instruments which are-accessible during operation shall be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST.

Fire detection which are not accessible during plant operation shall be demonstrated OPERABLE by the performance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless performed in the previous 6 months.

4.3.'3.8.2 The NFPA Standard 72D supervised circuits supervision associated ~

with the detector alarms of each of the above required fire detection instru-ments shall be demonstrated OPERABLE'at least once per 6 months.

4.3.3.8.3 The non-supervised circuits between the local fire protection panels and actuated equipment shall be demonstrated OPERABLE at least once per 6 months.

The fire detection instruments located within the containment are not required tc be OPERABLE during the performance of Type A Containment Leakage Rate Tests.

w'r UH - UNIT 2 3/4 3-59 f.mendr.ient No. 28

?

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 9.

Preservice Inspection means an inspection of the full length of each tube in each steam generator performed by eddy current techniques prior to service to establish a baseline condition of the tubing.

This inspection shall be performed prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections.

b.

The steam generator shall be determined OPERABLE after. completing the corresponding actions (plug all tubes exceeding the plugging limit and all tubes containing through-wall cracks) required by Table 4.4-2.

4.4.5.5 Reports a.

Following each inservice inspection of steam generator tubes, the number of tur s plugged in each steam generator shall be reported to the Commissir$ within 15 days.

b.

The complete results of the steam generator' tube inservice inspection shall be submitted to the Commission in a Special Report pursuant to

._ Specification 6.9.2 within 12 months following the completion of the inspection.

This Special Report shall include:

1.

Number and extent of tubes inspected.

2.

Location and percent of wall-thickness penetration for each indication of an imperfection.

3.

Identification of tubes plugged.

Results of steam generator tube inspections which fall'into Category c.

C-3 shall be reported pursuant to Specification 6.6.1 prior to resump-tion of plant operation.

The written followup of this report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.

$t(U'..11 - UNIT 2 3/4 4-14 Amendment ilo. 28 l-

a.

4 1

TABLE 4.4-2 c

?-

1

{

7 STEAM GENERATOR TUBE INSPECTION 1

4 C

i f:.

IST SAMPLE INSPECTION 2ND SAMPLE INSPECTION 3RD SAMPLE INSPECTION 1

-4 Lmple Size Result Action Required Result Action Required Reisult Action Required

,i g

A minimum of C-1 None N/A N/A N/A N/A I

S Tubes per S. G.

C-2 Plug defective tubes C-1 None N/A N/A j

.said iiigacct mklitiosial l* lug delective tutses C-1 Nuese 1

2S tutms in tinis S. G.

C. 2 amt inspect ailditional C-2 Plug defective tusses 45 tiehes in this S. G.

~

{

Perform actiust for C-3 C-3 result of first sample R

Perform action for C-3 C-3 result of first N/A N/A 9

sample g

C-3

!nspect all tubes in All other this S. G., plug de.

S. G.s are None N/A N/A factive tubes and.

C-1 inspect 2S tubes in Some S. G.s each other S. G.

Perform action for N/A N/A C-2 but no C-2 result of second additional sample Prompt notification S. G. are to NRC pursuant C-3 i

to specification Additional inspect all tubes in i

6.6.1 S. G. is C-3 each S. G. and plug defective tubes.

y i

Prompt notification N/A N/A 5

to NRC pursuant to specification 6.6.1 i

y S=3"% Where N is the riumber of steam generators in the unit, and n is the number of steam generators ' spected m

n during on inspation S

I 1

REACTOR COOLANT SYSTEM ACTION:

(Continued)

MODES 1, 2, 3, 4 and 5:

a.

With the specific activity of the primary coolant greater than 1.0 _ microcurie per gram DOSE EQUIVALENT I-131 or greater than 100/E microcuries per gram, perform the sampling and analysis requirements of item 4a of Table 4.4-4 until the specific activity of the primary coolant is restored to within its limits.

A SPECIAL REPORT shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days.

This report shall contain the results of the specific activity analyses together with the following information:

1.

Reactor power history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded, 2.

Fuel burnup by core region, 3,

Clean-up flow history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded, 4.

History of de gassing operations, if any, starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded, and 5.

The time duration when the specific activity of the primary coolant exceeded 1.0 microcurie per gram DOSE EQUIVALENT I-131.

SURVEILLANCE REQUIREMENTS 4.4.8 The specific activity of the primary coolant shall be determined to be within the limits by performance of the sampling and analysis program of Table 4.4-4.

~

SEQUD[i.B - L'!!!T 2 3/4 4-25 Amendment No. 28

o-EMERGENCY CORE COOLING SYSTEMS 3/4.5.2 ECCS SUBSYSTEMS - T,yg Greater Than or Equal to 350 F LIMITING CONDITION FOR OPERATION

^3.5.2 Two indepenc'bnt emergency core cooling system (ECCS) subsystems shall be OPERABLE with each subsystem comprised of:

a.

One OPERABLE centrifugal charging pump, b.

One OPERABLE safety injection pump, c.

One OPERABLE residual heat removal heat exchanger, d.

One OPERABLE residual heat removal pump, and An OPERABLE flow path capable of taking suction from the refueling e.

water storage tank on a safety injection signal and automatically transferring suction to the containment sump during the recirculation phase of operation.

APPLICABILITY:

MODES 1, 2 and 3.

ACTION:

With one ECCS subsystem inoperable, restore the inoperable subsystem a.

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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

In the event the ECCS is actuated and injects water into the Reactor Coolant System, a REPORTABLE EVENT shall be prepared and submitted to the Commission pursuant to Specification 6.6.1.

This report shall include a description of the circumstances of the actuation and the total accumulated actuation cycles to date.

The current value of the usage factor for each affected safety injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.

SURVEILLANCE REQUIREMENTS 4.5.2 Er.ch ECCS subsystem shall be demonstrated OPERABLE:

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the following valves are a.

in the indicated positions with power to the valve operators removed:

NOTE: With one centrifugal charging pump inoperable, the emergency core cooling system (ECCS) may remain operable for an additional 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months beyond that identified in Action statement (a).

This temporary change expires at 0848 on July 13, 1334.

SUH0ii.H - UNIl 2 3/4 5-5 Amendmen, No. 28

EMERGENCY CORE COOLING SYSTEMS 3/4.5.3 ECCS' SUBSYSTEMS - T,y LESS THAN 350*F LIMITING CONDITION FOR OPERATION 3.5.2 As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE:

a.

One OPERABLE centrifugal charging pump, b.

One OPERABLE residual heat removal heat exchanger, c.

One OPERABLE residual heat removal pump, and d.

An OPERABLE flow path capable of taking suction from the refueling water storage tank upon being manually realigned and atomatically transferring suction to the containment sump during t..

recirculation phase of operation.

APPLICABILITY:

MODE 4.

ACTION:

.-With no ECCS subsystem OPERABLE because of the inoperability of a.

either the centrifugal charging pump or the flow path from the refueling water storage tank, restore at least one ECCS subsystem to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months .

b.

With no ECCS subsystem OPERABLE because of the inoperability of either the residual heat removal heat exchanger or residual heat removal pump, restore at least one ECCS subsystem to OPERABLE status or maintain the Reactor Coolant System T"V9 less than 350*F by use of alternate heat removal methods.

c.

In the event the ECCS is actuated and injects water into the Reactor Coolant System, a REPORTABLE EVENT shall be prepared and submitted to the Commission pursuant to Specification 6.6.1.

This report shall include a description of the circumstances of the actuation and the total accumulated actuation cycles to date.

The current value of the usage factor for each affected safety injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.

SU.UQ UJi - UNIT 2 3/4 5-9 Amendment No. 28

o CONTAINMENT SYSTEMS CONTAINMENT VESSEL STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.6 The structeral integrity of the containment vessel shall be maintained

- at a level consistent with the acceptance criteria in Specification 4.6.1.6.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With the structural integrity of the containment vessel not conforming to the above requirements, restore the structural integrity to within the limits prior to increasing the Reactor Coolant System temperature above 200*F.

SURVEILLANCE REQUIREMENTS 4.6.1.6 The structural integrity of the containment vessel shall be deterrined during the shutdown for each Type A containment leakage rate test (reference Specification 4.6.1.2) by a visual inspection of the exposed accessible interior and exterior surfaces of the vessel This inspection shall be performed prior to the Type A containment leakage rate test to verify no apparent changes in appearance of the surfaces or other ' abnormal degradation.

Any abnormal degra-dation of the containment vessel detected during the above required inspec-tions shall be reported to the Commission pursuant to Specification 6.6.1.

I.

I SE. Z.AH - UNIT 2 3/4 6-11 Amendment No.

28

9 CONTAINMENT SYSTEMS SHIELD BUILDING STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION

3. 6. J. 7 The structural integrity of'the shield building shall be maintained at a level' consistent with the acceptance criteria in Specification 4.6.1.7.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With the structural integrity of the shield building not conforming to the above requirements, restore the structural integrity to within the limits prior to increasing the Reactor Coolant System temperature above 200 F.

SURVEILLANCE REQUIREMENTS 4.6.1.7 "The structural integrity of the shield building shall be determined during the shutdown for each Type A containment leakage rate test (reference Specification 4.6.1.2) by a visual inspection of the exposed accessible interior and exterior surfaces of the shield building and verifying no apparent changes in appearance of the concrete surfaces or other abnormal degradation.

Any abnormal degradation of the shield building detected during the above required inspections shall be reported to the Commission pursuant to Specification 6.6.1.

l I

SED"^i/M - L.iT 2 3/4 6-12 Amendment i:o. 28

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PLANT SYSTEMS 3/4.7.11 FIRE SUPPRESSION SYSTEMS FIRE SUPPRESSION WhTER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.11.1 The fire suppression water system shall be OPERABLE with:

a.

Two fire suppression pumps, each with a capacity of 1174 gpm, with their discharge aligned to the fire suppression header, and b.

An OPERABLE flow path capable of taking suction from the forebay and transferring the water through distribution piping with OPERABLE sectionalizing control or isolation valves to the yard hydrant curb valves, the last valve ahead of the water pressure alarm device on each sprinkler or hose standpipe, and the last valve ahead of the deluge valve on each deluge or spray system required to be OPERABLE per Specifications 3.7.11.2 and 3.7.11.4.

APPLICABILITY:

At all times.

ACTION:

a.

With only one pump 0.'ERABLE restore the inoperable equipment to OPERABLE status within 7 days or, in lieu of any other report required by Specification 6.6.1, prepare and submit a Special l

Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the plans and procedures to be used to restore the inoperable equipment to OPERABLE status or to provide an alternate backup pump or supply. 'The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

b.

With the fire suppression water system otherwise inoperable:

1.

Establish a backup fire suppression water system within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and 2.

In lieu of any other report required by Specification 6.9.1,.

submit a Special Report in accordance with Specification 6.9.2:

a)

By telephone within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b)

Confirmed by telegraph, mailgram or facsimile transmission no later than the first working day following the event, and SEQll'J#dt - Ul:IT 2 3/4 7-43 Amen +. cat I;o. 28

~

PLANT' SYSTEMS SPRAY AND/0R SPRINKLER SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.21.2 The following spray and/or' sprinkler systems shall be OPERABLE:

a.

Reactor Building - RC pump area, innulus b.

Auxiliary Building - Elev. 669, 690, 706, 714, 734, 749, 759, ABGTS Filters, EGTS Filters, Cont. Purge Filters, and 125V Battery Rooms.

~

c.

Control Building Elev. o69, Cab'e Spreading Room, MCR air filters, and operator living area.

d.

Diesel Generator Building - Corridor Area.

e.

Turbine Building - Control Building Wall.

APPLICABILITY:

Whenever equipment protected by the spray / sprinkler system is required to be OPERABLE.

ACTION:

a.

With one or more of the above required spray and/or sprinkler systems inoperable, within one hour establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant systems or components could be damaged; for other areas establish an hourly fire watch patrol.

Restore the system to OPERABLE status within 14 days or, in lieu of any other report required by Specifica-tion 6.6.1, prepare and submit a Special Report to the Commission l

pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

4 b.

The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.11.2 Each of the above required spray and/or sprinkler systems 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 is in its correct position.

b.

At least once per 12 months by cycling each testable valve in t'he flow path through at least one complete cycle of full travel, i

SL0tt0WJI - UNIT 2 3/4 7-45 Amendment No. 28 y

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-i PLANT SYSTEMS CO SYSTEMS 2

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LIMITING CONDITION FOR OPERATION

~

i 3.7.'11.3 The!following low pressure CO systems shall be OPERABLE.

2

- a.

Computer Room

[

b.

Auxiliary. Instrument Room-c.

Diesel Generator. Rooms d.

-Fuel Oil Pump Rooms' I

APPLICABILITY:.Whenever, equipment protected by the C0 systems is required to 2

l

-be OPERABLE.-

ACTION:

a.

With one or more of the above required CO systems inoperable, L

within'one hour establish a continuous fi,e watch with backup fire r

i suppression equipment for those areas in which redundant systems or' components could be damaged; for 'other areas, establish an hourly e

fire watch patrol.

Restore the system to OPERABLE status within 14 i'

days or, in lieu of any other report required by-Specification

- l 6.6.1, prepare.and submit a Special Report to the Commission pursuant' to Specification 6.9.2 within the next 30 days outlining the action-taken, the cause of the inoperability-and the plans and schedule for-j restoring the, system to OPERABLE status.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

j.

SURVEILLANCE REQUIREMENTS i-

{

4.7.11.3.1-Each of the above required C0 systems shall be demonstrated OPERABLEatleastonceper31daysbyver$fyingthat.eachvalve(manual, power.

t operated or automatic) in the flow path is in its correct position.

4.7.11.3.2 Each of the above required low pressure CO systems shall be-2 1

dr.pstrated OPERABLE:

i a.

At least once per 7 days by verifying the CO. storage tank level to begreaterthan50%andpressuretobegreat$rthan270psig,and i

b'.

At least once per 18 months by verifying:

)

1.

The system valves and associated ventilation dampers and fire I

i door release mechanisms actuate manually and automatically, upon receipt of a simulated actuation signal, and l

2.

Flow f rom each nozgle during a "Puf f Test."

3 s

H ? CC.u - UNIT 2 3/4 '7 I.ren&.K r.. No. 28 io

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PLANT SYSTEMS FIRE HOSE STATIONS LIMITING CONDITION FOR OPERATION 3.7.11.4 The fire hose stations shown in Table 3.7-5 shall be OPERABLE.

APPLJCABILITY: Whenever equipment in the areas protected by the fire hose stations is required to be OPERABLE.

ACTION:

a.

With one or more of the fire hose stations shown in Table 3.7-5 inoperable, route an additional equivalent capacity fire hose to the

~

unprotected area (s) from an OPERABLE hose station within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months if the inoperable fire hose is the primary means of fire suppression; other-wise, route the additional hose within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Restore the fire hose station to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.6.1, prepare and submit a Special

}

Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability, and plans and schedule for restoring the station to OPERABLE status, b.

The provisions of Specifications 3.0.3 and 3'.0.4 are not applicable.

SURVEILLAUCEREQUIREMENTS 4.7.11.4 Each of the fire hose stations shown in, Table 3.7-5 shall be demonstrated OPERABLE:

a.

At least once per 31 days by a visual inspection of the fire hose stations accessible during plant operations to assure all required equipment is at the station.

b.

At least once per 18 months by:

1.

Visual inspection of all the stations not accessible during plant operaticas to assure all required equipment is at the statiorr.

2.

Removing the hose for inspection and re-racking, and 3.

Inspecting all gaskets and replacing any degraded gaskets in the couplings.

c.

At least once per 3 years by:

1.

Partially opening each hose station valve to verify valve OPERABILITY and no flow blockage, i

2.

Conducting a hose hydrostatic test at a pressure of 300 psig or at least 50 psig above maximum fire main operating pressure, whichever is greater.

M O.~.Mi,H - UNIT 2 3/4 7-48 Atendment No.28

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PLANT SYSTEMS 3/4.7.12 FIRE BARRIER PENETRATIONS LIMITING CONDITION FOR OPERATION 3.7.12 All fire barrier penetrations (ir.cluding cable penetration barriers, firedoors and fire dampers) in fire zone boundaries protecting safety related areas, shall be functional.

APPLICABILITY:

At all times.

ACTION:

a.

With one or more of the above required fire barrier penetrations non-functional, within one hour either, establish a continuous fire watch on at least one side of the affected penetration, or verify the OPERABILITY of fire detectors on at least one side of the non-functional fire barrier and establish a hourly fire watch patrol.

Restore the non-functional fire barrier penetration (s) to functional status within 7 days or, in lieu of any other report required by Specification 6.6.1, prepare and submit a Special Report to the

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Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the non-functional pene-tration and plans and schedule for restoring the fire barrier penetration (s) to functional status, b.

The provisions of Specifications 3.0.3 and 3.0.4 are not cpplicable.

SURVEILLANCE REQUIREMENTS 4.7.12 Each of the above required fire barrier penetrations shall be verified to be functional:

a.

At least once per 18 months by a visual inspection, b.

Prior to returning a fire barrier penetration to functional status following repairs or maintenance by performance of a visual inspection of the affected fire barrier penetration (s).

t f r.. ( All - UMIT 2 3/4 7-52 Amendment No. 28

RADI0 ACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION 3.11.1.2 Tne dose or dose commitment to an individual from radioactive materials in liquid effluents released from the site (see Figure 5.1-1) shall be limited to the following*:

a.

During any calendar quarter to '

han or equal to 1.5 mrem to the total body and to less than c"

, to 5 mrem to any organ, and b.

During any calendar year to iest than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

~

a.

With the calculated dose f am the release of radioactive materials in liquid effluents exceeding any of the above limits, in lieu of

.any other report required b;.;ecification 6.6.1, prepare and submit l to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters, so that the cumulative dose or dose commitment to an individual from these releases is within 3 mrem to the total body and 10 mrem to any organ.

This Special Report shall also include (1) the results of radiological analyses of the drinking water source and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR 141, Safe Drinking Water Act, b.

The provisions of specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.2 Dose Calculations.

Cumulative dose contributions from liquid effluents shall be determined in accordance with the ODCM at least once per 31 days.

7.h n.ctor unit Si a f < - Utili 2 3/4 11-5 Amendtant No.28

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RADI0 ACTIVE EFFLUENTS '

LIQUID WASTE TREATMENT LIMITING CONDITION FOR OPERATION ~

,#I 3.11.1.3 beli~quidradwastetreatmentsystemshallbeOPERABLE. The appro-priate portions of the system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent from the site (see Figure 5.1-1) when averaged over 31 dpys.o would exceed 0.06 mrem to the total body or 0.2 mrem to any organ *.

.'j APPLICABILITY:.At all times.

o.

ACTION:

i With tNe liquid radwaste treatment system inoperable for more than a.

- 31 days o.r with radioactive 1.lquid weste being discharged without treatment end in excess of the abovei limits, in lieu of any other reporg.requ. ired by Specification 6.6.1, prepare-and submit to the l

Commission'within 30 days pursuant to Specification 6.9.2 a Special Report'which includes the following information:

1.

Identification of the inoperable equipment or subsystems and the reason for inoperability, 2.

Action (s) taken to restore the inoperable equipraant to OPERABLE status, and' 3.

Summary description of action (s) taken to prever.tia recurrence.

~

b.

The provisions of Specifications 3.0.3 and 3.024 are not applicable.'

/

SURVEILLANCE REQUIREMENTS

~

4.11'.1.3.1 Doses due to l'iquid releeses shall be projected'at least once per 31 days, in accordance with the 00CM.,

4.11.1.3.2 The liquid radwaste treatment systre shall be demonstrated OPERABLE by operating the liquid radwaste treatment system equipment for at least 15 minutes at least once per'32 days unless the liquid ~ radwaste syster, has been" utilized to proces,s radioactive liquid effluents during the previous 92 daps.

s E reactur unit SEU:.Vidi - UNil 2 3/4 1 -6 hraendment I!o.

28 S

4,1,

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~RADI0 ACTIVE EFFLUENTS DOSE - NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.2 The air dose due to noble gases released in gaseous effluents.from the site (see Figure 5.1-1) shall be limited to the following*:

a.

During any calendar quarter:

Less than or equal to 5 mrad for gamma' radiation and less than or equal to 10 mrad for beta radiation and, b.

During any calendar year:

Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

APPLICABILITY:

At all times.

ACTION a.

With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, in lieu of any other report required by Specification 6.6.1, prepare and submit to the l

.. Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases of radioactive noble gases in gaseous effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters, so that the cumulative dose is within 10 mrad for gamma radiation and 20 mrad for beta radiation.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.2 Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with the ODCM at.least once per 31 days.

Per reactor unit.

SEQUO.-

- U: IT 2 3/4 11-12

/.c;endt.ent No. 28 J

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RADI0 ACTIVE EFFLUENTS DOSE-RADIOI0 DINES,RADI0ACTIVEMATERIALSINPARTICULATEFORM,ANbRADIONUCLIDES OTHER THAN N0BLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to an individual from radioicdines and radioactive materials in particulate form, and radionuclides (other than noble gases) with half-lives greater than 8 days in gaseous effluents released from the site (see Figure 5.1-1) shall be limited to the following*:

a.

During any calendar quarter:

Less than or equal to 7.5 mrem to any organ and, b.

During any calendar year:

Less than or equal to 15 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

a.

With the calculated dose from the release of radioiodines, radioactive materials in particulate form, or radionuclides (other than noble gases) with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, in lieu of any other report required by Specification 6.6.1, prepare and submit to the Commission l within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions to be taken to reduce the releases of radio-iodines and radioactive materials in particulate form, and radio-nuclides (other than nobles gases) with half-lives greater than 8 days in gaseous effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters, so that the cumulative dose or dose commitment to an individual from these releases is within 15 mrem to any organ.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.3 Dose Calculations Cumulative dose contributions for the current calendar. quarter and current. calendar year shall be determined in accordance with the ODCM at least once per 31 days.

Per reactor unit.

11]CVAH - UNIT 2 3/4 11-13 Amendment No.28

RADI0 ACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT LIMITING CONDI'iION FOR OPERATION 3.11.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE.

The appropriate portions of the GASEOUS RADWASTE TREATMENT SYSTEM shall be used to reduce radioactive materials in j

gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases from the site (see Figure 5.1-1), when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation *.

The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases from the site (see Figure 5.1-1) when averaged over 31 days would exceed 0.3 mrem to any organ.*

APPLICABILITY:

At all times.

ACTION:

a.

With ti GASEOUS RADWASTE TREATMENT SYSTEM and/or the VENTILATION

.EXHAUSY TREATMENT SYSTEM inoperable for more than 31 days or with gaseous waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by Specifica-tion 6.6.1, prepare and submit to the Commission within 30 days, l

pursuant to Specification 6.9.2, a Special Report which includes the following information:

1.

Identification of the inoperable equipment or subsystems and the reason for inoperability, 2.

Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3.

Summary description of action (s) taken to prevent a recurrence.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due tc gaseous releases from the site shall be projected at least once per 31 days, in accordance with the ODCM.

4.11.2.4.2 The GASEOUS RADWASTE TREATMENT SYSTEf1 and VENTILATION EXHAUST TREAT-MENT SYSTEM shall be demonstrated OPERABLE by operating the GASE0US RADWASTE TREATMENT SYSTEM equipment and VENTILATION EXHAUST TPEATHENT SYSTEM equipment

!cr et least 15 minutes, at least once per 92 days unless the appropriate system has been utilized to process radioactive gaseous effluents during the previous 92 days.

t a n e s. : t : are per reactor unit.

SEQUOGH -

t SIT 2 3/4 11-14 Amendment No. 28

RADI0 ACTIVE EFFLUENTS 3/4.11.3 SOLID RADIOACTIVE WASTE LIMITING CONDITION FOR OPERATION 3.11.3 The solid radwaste system shall be OPERABLE and used, as applicable in accordance with a PROCESS CONTROL PROGRAM, for the SOLIDIFICATION and packaging of radioactive wastes to ensure meeting the requirements of 10 CFR Part 20 and of 10 CFR Part 71 prior to shipment of radioactive wastes from the site.

APPLICABILITY:

At all times.

ACTION:

a.

With the packaging requirements of 10 CFR Part 20 and/or 10 CFR Part 71 not satisfied, suspend shipments of defectively packagau solid radioactive wastes from the site.

b.

With the solid radwaste system inoperable for more than 31 days, in lieu of any other report required by Specifigation 6.6.1, prepare and l

submit to the Commission within 30 days pursuant to Specification 6.9.2 a Special Report which includes the following information:

l.

Identification of the inoperable equipment or subsystems and the reason for inoperability, 2.

Action (s) taken to restore the inoperable equipment to OPERABLE status, 3.

A description of the alternative used for SOLIDIFICATION and packaging of radioactive wastes, and 4.

Summary description of action (s) taken to prevent a recurrence.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.3.1 The. solid radwaste system shall be demonstrated OPERABLE at least once per 92 days by:

a.

Operating the solid radwaste system at least once in the previous 92 days in accordance with the PROCESS CONTROL PROGRAM, or b.

Verification of the existence of a valid contract for SOLIDIFICATION to be perforn.ed by a contractor in accordance with a PP.0 CESS CONTROL PROGRAM.

.SEQUOYAH - UMIT.2 3/4 11-17 Amendment No. 28

o RADI0 ACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE LIMITING CONDITION FOR OPERATION 3.11.4 The dose or dose commitment to any member of the public, due to releases of radioactivity from uranium fuel cycle sources, shall be limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrem) over 12 consecutive months.

1 APPLICABILITY: At all times.

l l

ACTION:

a.

With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifica-tions 3.ll.l.2.a, 3.ll.1.2.b, 3.11.2.2.a, 3.ll.2.2.b, 3.11.2.3.a, or 3.11.2.3.b, in lieu of any other report required by Specification 6.6.1, l

prepare and submit a Special Report to the Director, Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commissi' n, Washington, D.C.

o 20555, within 30 days, which defines the corrective action to be taken

.to reduce subsequent releases to prevent recurrence of exceeding the limits of Specification 3.11.4.

This Special Report shall include an analysis which estimates the radiation exposure (dose) to a member of the public from uranium fuel cycle sources (including all effluent pathways and direct radiation) for a 12 consecutive month period that includes the release (s) covered by this moport.

If the estimated dose (s) exceeds the limits of Specification 3.11.4, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40,CFR 190 and including the specified information of g 190.11(b).

The variance only relates to the limits of 40 CFR 190, and does not apply in any way to the requirements for dose limitation of 10 CFR Part 20, as addressed in other sections of this technical specification.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.4 Dose Calculations Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Specifications 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the ODCM.

SEQUuI H - UM11 2 3/4 11-19 Amendn.ent No. 23

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 1

3.12.1 The radiological environmental monitoring program shall be conducted as-specified in Table 3.12-1.

APPLICABILITY:

At all times.

ACTION:

a.

With the radiological environmental monitoring program not being

~

conducted as specified in Table 3.12-1, in lieu of any other report required by Specification 6.9.1 or 6.6.2, prepare and submit to the l

Commission, in the Annual Radiological Operating Report, a descrip-tion of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b.

With the 'evel of radioactivity in an environmental sampling medium exceeding the reporting levels of Table 3.12-2 when averaged over any calendar quarter, in lieu of any other report required by Specification 6.9.1 or 6.6.1, prepare and submit

to the Commission

.l within 30 days from the end of the affected calendar quarter a Report' pursuant to Specificiation 6.9.1.13.

When more than on.e of the radio-nuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitted if:

concentration (1) concentration (2) + **'> 1.0 limit level (1) limit level (2)

When radionuclides other than those in Table'3.12-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to an individual is equal to or greater than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3.

This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an avent, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

c.

With milk or fresh leafy vegetable samples unavailable from one or

~

more of the sample locations required by' Table 3.12-1, in lieu of any other report required by Specification 6.9.1 or 6.6.1, prepare l

and submit to the Commission within 30 days, pursuant to Specifica-tion 6.9.2, a Special Report which identifies the cause of the unavailability of samples and identifies locations for obtaining replaccrent samples.

The locations from which san:ples were unavail-able may then be deleted from those required by. Table 3.12-1, provided the locations from which the replacement samples were obtained are added to^the environmental monitoring program as replacement locations.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are'not applicabl?.

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L- :,.:.1 report ;2ursuant to specification 6.9.2.

SE000iAH - UMIT 2 3/4 12-1 Amendment No. 28

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RADIOLOGICAL ENVIRONSENTAL MONITORING

'3/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2 A land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence and the nearest garden

of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteoro-logical sectors within a distance of five miles.

(For elevated releases as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use census shall also identify the locations of all milk animals and all gardens of greater j

than 500 square feet producing fresh leafy vegetables in each of the 16 meteoro-logical sectors within a distance of three miles.)

APPLICABILITY:

At all times.

ACTION:

a.

With a land use census identifying a location (s) which yields a calcu-lated dose or dose commitment greater than the maximum value currently being calculated in Specification 4.11.2.3.1, in lieu of any other report required by Specification 6.6.1., prepare and submit to the Commission l

within 30 days after the updated calculation, pursuant to Specific-ation 6.9.2, a Special Report which identifies the new location (s).

b.

With a land use census identifying a location (s) which yields a calcu-lated dose or dose commitment (via the same exposure pathway) 20 percent greater than the highest calculated dose or dose commitment at a location "from which samples are currently being obtained in accordance with Speci-fication 3.12.1, in lieu of any other report required by Specifi-cation 6.6.1, prepare and submit to the Commission within 30 days after

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the updated calculation, pursuant to Specification 6.9.2, a Special Report which identifies the new location.

The new location shall be added to the radiological environmental monitoring program within 30 days, if the owner consents.

The sampling location, excluding the control station location, having the lowest calculated dose or dose commitment (via the same exposure pathway) may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.2 The land use census shall be conducted at least once per calendar year between the dates of April 1 and October 1 using the following techniques:

1.

Within a 2-mile radius from the plant or within the 15-mrem / year isodose line, whichever is larger, enumeration by a door-to-door or equivalent counting technique.

2.

. With a 5-mile radius from the plant, enumeration by using appropriate techniques such as door-to-door survey, mail survey, telephone survey, s'erial servey, or information from local agricultural authorities or outer reliable sources.

7Eivou leaf vegetation snmpling may be performed at the site boundary in the d?

,' " rector with the t. phest D/Q in lieu of the garden census.

SEQUO?AH - UNIT 2 3/4 12-10 Amendment No. 28

ADMINISTRATIVE CONTROLS d.

Review of proposed changes to the Technical Specifications related to radiological assessments involving dose calculations and projections and environmental monitoring.

Authority 6.5.3.7 The RARC shall:

a.

Recommend in writing to the Chief, Radiological Hygiene Branch approval or disapproval of items considered under 6.5.3.6 above.

b.

Render determinations in writing with regard to whether or not each item considered under 6.5.3.6 constitutes an unreviewed safety question.

c.

Provide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Director, Nuclear Power Division and the Nuclear Safety Review Board of disagreement between the RARC and the Chief, Radiological Hygiene Branch; however, the Chief, Radiological Hygiene Branch shall have responsibility for 1

resolution of such disagreement pursuant to 6 1.2 above.

Records 6.5 3.8 The RARC shall maintain written minutes of each RARC meeting that at a minimum, document the results of all RARC activities performed under the responsibility and authority provisions of these technical specifications.

Copies shall be provided to the Director, Nuclear Power Division, PORC, and the Nuclear Safety Review Board.

6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a.

The Commission shall be notified and/or a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and b.

Each REPORTABLE EVENT shall_be reviewed by the PORC and the results of this review shall be submitted to the NSRB and the Director, Nuclear

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Power Division.

6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a.

The unit shall be placed in at least HOT STANDBY within one hour.

b.

The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour.

The Director, Nuclear Power Division and the N5RB shall be notified with 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

- SE:;UOYAll - UNIT 2 6-17 Amendment No. 28

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ADMINISTRATIVE CONTROLS 6.9 REPORTING REQUIREMENTS l

ROUTINE REPORTS

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6.9.4 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Director 4

of the Regional Office of Inspection and Enforcement unless otherwise noted.

i STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) mcdifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the

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FSAR and shall include a description of the measured values of the operating

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conditions or cnaracteristics obtained during the test. program and a comparison of these values with design predictions and specifications.

Any corrective j

actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.

I 6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial' 4

criticality, whichever is earliest.

If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until-all.three_ events "

l have been completed.

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l l-1 SEQUOVAi! - LN1T 2 6-21 Arc.enoment. No. 28

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.o ADMINISTRATIVE CONTROLS The radioactive effluent release report to be submitted 60 days after January 1 of.each year shall also include an assessment of radiatio'n doses to the likely most exposed members of the public from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiati0n) for the previous 12 consecutive months to show conformance with 40 CFR 190, Environmental CTdiation Protection Standards for Nuclear Power Operation.

Acceptable methods for calculating the dose contribution from liquid and gaseous. effluents are given in Regulatory Guide 1.109, Rev. 1.

The radioactive effluent release reports shall include the following information for each type of solid waste shipped offsite during the report period:

a.

Container volume, b.

Total curie quantity (specify whether determined by measurement or estimate),

c.

Principal radionuclides (specify whether determined by measurement or estimate),

d.

Typeofwaste(e.g.,spentresin,compactedSrywaste, evaporator bottoms),

Type of container (e.g., LSA, Type A, Type B, Large Quantity), and e.

f.

SOLIDIFICATION agent (e.g., cement, urea formaldehyde).

The radioactive effluent release reports shall include unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents on a quarterly basis.

The radioactive effluent release reports shall include any changes to the PROCESS CONTROL PROGRAM (PCP) made during the reporting period.

MONTHLY REACTOR OPERATING REPORT 6.9.1.10 Routine reports of operating statistics and shutdown experience, incl-uding documentation of all challenges to the PORVs or Safety Valves, shall be submitted on a monthly basis to the Director, Office of Management and Program Analysis, U.S.' Nuclear Regulatory Commissi6n, Washington, D.C.

20555, with a copy to the Regional Office of Inspection and Enforcement, no later than the 15th of each month following the calendar month covered by the report.

Any changes' to the OFFSITE DOSE CALCUL TION f1ANUAL shall be submitted with the lionthly' Operating Report within 90 days in which the chance (s).ms made effective.

In addition, a report of any major changes to the radioactive waste treatment systems shall be submitted with the Monthly Operating Report for the period in which the evaluation was reviewed and_ accepted by the PORC.

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SE N,Ali - UNIT 2 6-24 Amendment No. 28

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THIS PAGE DELETED Sf ' J01/.ti - UNIT 2 6-25 Amert& tent i,'o.

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SE,!UOYUi - UfJIT 2 6-26 f.mendment l'o.

33

9 ADMINISTRATIVE CONTROLS RADIAL PEAKING FACTOR LIMIT REPORT 6.9.1.14 The W(z) function for normal operation shall be provided to the Director, Nuclear Reactor Regulation, Attention, Chief of the Core Perfarmance Branch, U.S. Nuclear Regulatory Commission, Washington, D.C.

20555 at least 60 days prior to cycle initial criticality.

In the event these values would be submitted at some other time'during core life, it will be submitted 60 days prior to the date the values would beceme effective unless otherwise exempted by the Commission.

1 Any information needed to support W(z) will be by request from the NRC and need -not be included in this report.

SPECIAL REPORTS' 6.9.2 Special reports shall be submitted to the Director of the Office of Inspection and Enforcement Regional Office within the time period specified for each report.

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6.10 RECORD RETENTION In addition to the applicable record retention requirements of Title 10, Code of FederaLRegulations, the following records shall be retained for at least the minimum period indicated.

1 6.10.1 The following records shall be retained for at least five years:

a.

Records and logs of unit operation covering time interval at each power level.

.b.

Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.

c.

All REPORTABLE EVENTS subritted to the Commission.

d.

Records of surveillance activities, inspections and calibrations required by these Technical Specifications.

e.

Records of changes made to the procedures required by Specification 6.8.1 and 6.8.4.

f.

Reccrds of radioactive shipments.

n.

Records of scaled source and fission detector. leak tests and results.

h.

Records of. annual physical inventory of all sealed source material of record.

SE000YAH - UNIT 2 6-27 Amendment No. 28

e ADi1INISTRATIVE CONTROLS 6.10.2 The following records shall be retained for the duration of the Unit Operating License:

a.

Records and drawing changes reflecting unit design modifications made to systems and equipment described in the Final Safety Analysis Report.

b.

Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

c.

Records of radiation exposure for all individuals entering radiation control areas.

d.

Records of gaseous and liquid radioactive material released to the environs.

e.

Records of transient or operational cycles for those unit components identified in Table 5.7-1.

I t.

Records of reactor te'sts and experiments.

g.

Records of training and qualification for current members of the unit staff.

h.

Records of in-service inspections performed pursuant to.these Technical Specifications.

i.

Records of Quality Assurance activities required by the Operational Quality Assurance Manual.

j.

Records of reviews performed for changes madd to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

k.

Records of meetings of the PORC, RARC, and the NSRB.

1.

Records of analyses required by the radiological environmental monitoring program.

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'SEQUOYAH - UNIT 2 6-28 Amendment No. 28

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