Text

Amends 66 & 66 to Licenses NPF-87 & NPF-89,respectively, Correcting Number of Editorial Errors in TSs That Occurred with Issuance of License 64 Re ITSs Conversion
	ML20210N158
Person / Time
Site:	Comanche Peak
Issue date:	08/03/1999
From:	Gramm R; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML20210N161	List: ML20210N158; ML20210N170;
References
	NUDOCS 9908110036
	Download: ML20210N158 (30)
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,S UNITED STATES

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j NUCLEAR REGULATORY COMMISSION p

2 WA$HINGToN, D.C. 20556 0001 i

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IEXfAS UTILITIES ELECTRIC coy.PANY l

COMANCHE PEAK STEAM EiLECTRIC STATl_QN. UNIT 1 DOCKET NO. 50-445 AMENDPflgNTIQfACILITY OPE!iATING LICENSE Amendment No. 66 License No. NPF 87 1.

The Nucler.r Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Texas Lrtilities Electric Company (TU Electric, the licensee) dated May 4,1999, as r,upplemented by tetter d3%d June 4,1999, com,alies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and tits Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commissiorr, C.

There is reasonable assurance (i) that the activities au'horized by this amendment can be conducted without endangering the heahh and safety of the public, and (ii) that such activities will be conducted in complianca with the

' Commission's regulations; D.

The issuance of this license amendment wJll not be inimical to the common defersse and security or to the health and safety of the public; and E.

The issuance of thic. cmendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated !n the attachment to this license amenc:rnent and Paragraph 2.C.(2) of Facility i

Operating Licente No NPF-87 is hereby amended to read as follows:

l 9908110036 990E03 PDR ADOCK 05000445 P

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Technical Specificatiqns andJnvimnmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment Noc 66

, and the Environmental Protection Plan contained in Appendix B, ooth of which are attached hereto, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Ensironmental Protection Plan.

3.

The license amendment is effective as of its date of issuance and shall be implemented I

within 30 days from the date of issuance.

l FOR THE NUCLEAR REGULATORY COMMISSION Robert A. Gramm, Chief, Section 1 Project Dir9ctorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications j

Date of Issuance:

August 3, 1999 I

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UNITED STATES 3

j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20665-0001

.....,d TEXAS UTILITIES ELECTRIC COMPANY COMANCHE PEAK STEAM ELECTRIC STATION UNIT 2 DOCKET NO. 50-446 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 66 License No. NPF-89 1.

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

A.

The application for amendment by Texas Utilities Electric Company (TU Electric, the licensee) dated May 4,1999, as supplemented by letter dated June 4,1999, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that sucn activities will be conducted in compliance with the Commission's regulations:

D.

The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and I

I E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as j

indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-89 is hereby amended to read as follows:

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Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.

66, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. TU Electric shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance and shall be implemented

. within 30 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION A hw Robert A. Gramm, Chief, Section 1 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications i

Date of issuance: August 3, 1999 1

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i ATTACHMENT TO LICENSE AMENDMENT NOS. 66 AND 66 j

FACILITY OPERATING LICENSE NOS. NPF-87 AND NPF-89 DOCKET NOS. 50-445 AND 50-446 i

Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain margina!

lines indicating the areas of change.

Remove insert 3.0-5 3.0-5 3.1-19 3.1-19 3.2-6 3.2-6 3.2 13 3.2-13 3.3-11 3.3-11 3.3-45 3.3-45 3.4-24 3.4-24 3.4-25 3.4-25 3.4-38 3.4 38 3.7-23 3.7-23 3.7-27 3.7-27 3.7-30 3.7-30 3.8-8 3.8-8 3.8-11 3.8-11 3.8-12 3.8-12 3.8-16 3.8-16 3.8-21 3.8-21 3.8-25 3.8-25 3.8-26 3.8-26 3.8-34 3.8-34 3.9-9 3.9-9 3.9-10 3.9-10 4.0-2 4.0-2 5.0-27 5.0-27 5.0-29 5.0 29 l

PHYSICS TESTS Exceptions-MODE 2 3.1.8 3.1 REACTIVITY CONTROL SYSTEMS 3.1.8 PHYSICS TESTS Exceptions - MODE 2 LCO 3.1.8 During the performance of PHYSICS TESTS, the requirements of LCO 3.1.3," Moderator Temperature Coefficient (MTC)";

LCO 3.1.4," Rod Group Alignment Limits";

LCO 3.1.5, " Shutdown Bank insertion Limits";

LCO 3.1.0, " Control Bs.nk Insertion Limits"; and

{

LCO 3.4.2, "RCS Minimum Temperature for Criticality" j

i may be suspended, provided:

a.

RCS lowest operating loop average temperature is a 541"F; and I

b.

SDM is within the limits provided in the COLR; and c.

THERMAL POWER is s 5% RTP I

APPLICABILITY:

MODE 2 durira PHYSICS TESTS.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

{

j A. SDM not within limit.

A.1 Initiate boration to restore 15 minutes l

SDM to within limit.

AND A.2 Sustend PHYSICS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months TESTS exceptions.

B. THERMAL POWER not B.1 Open reactor trip immediately within limit.

breakers.

(continued)

COMANCHE PEAK - UNITS 1 AND 2 3.1-19 Amendment No. 66

P SR Applicability 3.0 i:

3.0- SR APPLICA81L11Y '(continued)

SR 3.0.3 h *. is discovered that a Surveillance was not performed within its j

specified Frequency, then compliance with the requirement to declare the j

LCO not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified Frequency, whichever is less. 7is delay period is permitted to allow performance of the Surveillance.

If the Surveillance is not performed within the delay period, the LCO must immediately be declared not met, and the applicable Condition (s) must be entered.

When the Surveillance is performed within the delay period and the Suxei!!ance is not met, the LCO must immediately be declared not met, and the applicable Condition (s) must be entered.

SR 3.0.4 Entry into a MODE or other specified condition in the Applicability of an LCO shall not be made unbss the LCO's Surveillances have been met within their specified Frequency. This provision shall not prevent entry 1

' into MODES or other specified cionditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

SR 3.0.4 is only applicable for entry into a MODE or other specifed condition in the Applicability in MODES 1,2, 3, and 4.

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COMANCHE PEAK-UNITS 1'AND 2 3.0-5 Amendment No. 66

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3.2.2

' 3.2 POWER DISTRIBUTION LIMITS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F%s)

LCO 3.2.2 F%s shall be within the limits specified in the COLR.

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APPLICABILITY:

MODE 1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

NOTE A.1.1 Restore F2s to within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Required Actions A.2 limit.

and A.3 must be completed whenever Condition A is QB entered.

A.1.2.1 Reduce THERMAL-4 hours POWER to < 50% RTP.

F%s not within limit.

'M 4

A.1.2.2 Reduce Power Range 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Neutron Flux-High trip setpoints to s 55% RTP.

A.2 Perform ER 3.2.2.1.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months M

(continued) i i

COMANCHE PEAK - UNITS 1 AND 2 3.2-6 Amendment No. 66 Y

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QPTR 3.2.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.4 Reevaluate safety Prior to increasing analyses and confirm THERMAL POWER results remain valid for above the limit of duration of operation Required Action A.1 under this condition.

AMQ A.5 NOTES

1. Perform Required Action A.5 only after Required Action A.4 is completed.

2. Required action A.6 shall be completed l

whenever Required Action A.S is performed.

Normalize excore Prior to increasing detectors to restore THERMAL POWER QPTR to within limit.

above the limit of Required Action A.1 AMQ (continued)

' COMANCHE PEAK - UNITS 1 AND 2 3.2-13 Amendment No. 66

1 RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.5 Perform ACTUATION LOGIC TEST.

31 days on a STAGGERED TEST BASIS SR 3.3.1.6 -

NOTE Not required to be performed until 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after achieving equilibrium conditions with THERMAL POWER 2 75 % RTP.

Calibrate excore channels to agree with incore detector 92 EFPD measurements.

.SR 3.3.1.7 NOTES j

1. Not required to be performed for source range instrumentation prior to entering MODE 3 from MODE 2 until 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after entry into MODE 3.

2. Source range instrumentation shallinclude verification that interlocks P-6 and P-10 are in their required state for existing unit conditions.

Perform COT.

92 days (continued) l I

COMANCHE PEAK - UNITS 1 AND 2 3.3-11 Amendment No. 66

y LOP DG Start Instrumentation 3.3.5 ACTIONS (contir:ued)

CONDITION REQUIRED ACTION COMPLETION TIME 1

i D. Two channels per bus for D.1 Restore one channel per 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the 6.9 kV bus bus to OPERABLE undervoltage function status.

l inoperable.

DE D.2 Declare the affected A.C.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months emergency buses inoperable.

E. Two channels per bus for E.1 Restore one channel per 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months one or more degraded bus to OPERABLE voltage or low grid

status, undervoltage function inoperable QB E.2.1 Declare both offsite 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months power source buses inoperable.

ANQ E.2.2 Open offsite power 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months source breakers to the associated buses.

F. One or more Automatic F.1 Restore train (s) to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Actuation Logic and OPERABLE status.

Actuation Relays trains l

inoperable.

'G. Required Action and G.1 Enter applicable immediately associated Completion Condition (s) and Time not met.

Required Action (s) for the associated DG made inoperable by LOP DG start instrumentation.

COMANCHE PEAK-UNITS 1 AND 2 3.3-45 Amendment No. 66 i

Pr:ssurizar PORVs 3.4.11 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One block valve NOTE inoperable.

Required Actions do not apply l

when block valve is inoperable l

solely as a result of complying with Required Actions B.2 or E 2.

l C.1 P: ace associated PORV 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months in manual control.

M C.2 Restore block valve to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

D. Required Action and D.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A, B, E

or C not met.

D.2 Be in MODE 4 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (continued) l f

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COMANCHE PEAK - UNITS 1 AND 2 3.4-24 Amendment No. 66 i

Pressuriz::r PORVs 3.4.11

=

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Tw ; PORVs inoperable E.1 Close associated block 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and not capable of being valves.

manually cycled.

M E.2 Remove power from 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated block valves.

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1 E.3 Be in MODE 3 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months M

E.4 Be in MODE 4 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months F. More than one block valve NOTE inoperable.

Required Actions do not apply when block valve is inoperable solely as a result of complying with Required Actions B.2 or E.2.

F.1 Place associated PORVs 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months in manual control.

M F.2 Restore one block valve 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to OPERABLE status (continued)

COMANCHE PEAK - UNITS 1 AND 2 3.4-25 Amendment No. 66

RCS PlV Leakage 3.4.14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.14.1 NOTES 1.

Not required to be performed in MODES 3 and 4, 2.

Not required to be performed on the RCS PlVs located in the RHR flow path when in the shutdown cooling mode of operation.

3.

RCS PlVs actuated during the performance of this Surveillance are not required to be tested more than once if a repetitive testing loop cannot be avoided.

Verify leakage from each RCS PlV is equivalent to in accordance s 0.5 gpm per nominalinch of valve size up to a with the Inservice maximum of 5 gpm at an RCS pressure 2 2215 psig Testing Program, and s 2255 psig.

and 18 months i

AND Prior to entering MODE 2 whenever the unit has been in MODE 5 for 7 days or more, and if leakage testing has not been performed in the previous 9 months except for valves 8701 A, 8701B,8702A and 87028 AND (continued) t COMANCHE PEAK - UNITS 1 AND 2 3.4-38 Amendment No. 66

CREFS 3.7.10 3.7 PLANT SYSTEMS 3.7.10 Control Room Emergency Filtration / Pressurization System (CREFS) t LCO 3.7.10 Two CREFS trains shall be OPERABLE f

NOTE The Control Room boundary may be opened intermittently under administrative controls.

APPLICABILITY:

MODES 1,2,3,4,5, and 6, l

During movement of irradiated fuel assemblies ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CREFS train A.1 Restore CREFS train to 7 days inoperable.

OPERABLE status.

B. Two CREFS Trains B.1 Restore control room 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inoperable due to boundary to OPERABLE inoperable Contrcl Room status.

boundary in MODES 1,2, 3, and 4.

C. Required Action and C.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A or B AblQ not met in MODE 1,2,3, or 4.

C.2 Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

COMANCHE PEAK - UNITS 1 AND 2 3.7-23 Amendment No. 66

CRACS 3.7.11 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Two CRACS trains D.1.1 Verify at least 100% of immediately inoperable in MODE 5 or 6, the required heat removal or during movement of capability equivalent to n irradiated fuel assemblies, single OPERABLE train l

available.

M D.1.2 Restore the CRACS 30 days trains to OPERABLE status.

2 D.2.1 Suspen'd CORE Imrnediately ALTERATIONS.

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D.2.2 Suspend movement of immediately irradiated fuel assemblies.

E. Two CRACS trains E.1.1 Verify at least 100% of immediately inoperable in MODE 1,2,3, the required heat removal or 4.

capability equivalent to a single OPERABLE train available.

M E.1.2 Restore one CRACS train 30 days to OPERABLE status.

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i E.2 Enter LCO 3.0.3.

!mmediately COMANCHE PEAK - UNITS 1 AND 2 3.7-27 Amendment No. 66

PPVS - ESF Filtration Trains 3.7.12 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Actions and D.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Times not met.

ANQ D.2 Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVElLLANCE REQUIREMENTS SURVEILLANCE FREQUENCY l

SR 3.7.12.1 Operate each ESF Filtration train for 210 continuous 31 days hours with the heaters operating.

SR 3.7.12.2 Perform required ESF Filtration Unit filter testing in in accordance accordance with the Ventilation Filter Testing Program with tne VFTP (VFTP).

SR 3.7.12.3 Verify each PPVS train actuates on an actual or 18 months simulated actuation signal.

SR 3.7.12.4 Verify one PPVS train can maintain a pressure 18 months on a s - 0 95 inches water gauge relative to atmospheric STAGGERED l

pressure during the post accident mode of operation.

TEST BASIS (continued)

COMANCHE PEAK - UNITS 1 AND 2 3.7-30 Amendment No. 66

9 AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.4 Verify each day tank contains a 1440 gal of fuel oil.

31 days i

SR 3.8.1.5 Check for and remove accumulated water from each day 31 days tank.

SR 3.8.1.6 Verify the fuel oil transfer system operates to 92 days automatically transfer fuel oil from storage tank to the day tank.

SR 3.8.1.7 NOTE

. All DG starts may be preceded by an engine prelube period.

Verify each DG starts from standby condition and 184 days achieves:

l

a. in s 10 seconds, voltage 26480 V and frequency a 58.8 Hz; and

b. steady state, voltage a 6480 V and s 7150 V, and frequency a 58.8 Hz and s 61.2 Hz.

NOTE SR 3.8.1.8 Verify requirement during MODES 3,4,5,6 or.vith core off-loaded.

Verify automatic and manual transfer of AC power 18 months sources from the normal offsite circuit to each attemate required offsite circuit.

(continued)

Amendment No. 66 COMANCHE PEAK-UNITS 1 AND 2 3.8-8 i

n AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.12 NOTES

1. All DG starts may be preceded by prelube period.

2. Verify requirement during MODES 3,4,5,6 or with core off-loaded.

' Verify on an actual or simulated Safety injection (SI) 18 rronths actuation signal each DG auto-starts from standby condition and:

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a. In s 10 seconds after auto start and during tests, achieves voltage 2 6480 V and frequency 2 58.8 Hz; b.

Achieves steady state voltage 2 6480 V and s 7150 V and frequency a 58.8 Hz and s 61.2 Hz;

c. Operates for 2 5 minutes; SR 3.8.1.13 NOTE Verify requirement during MODES 3,4,5,6 or with core off-loaded.

Verify each DG's automatic trips are bypassed on 18 months actual or simulated loss of voltage signal on the

emergency bus concurrent with an actual or simulated Si actuation signal except;

a. Engine overspeed; and

b. Generator differential current.

(continued) i COMANCHE PEAK - UNITS 1 AND 2

' 3.8-11 Amendment No. 66 m.

r-AC Sources-Opercting 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.14 NOTES

1. Momentary transients outside the load and power factor ranges do not invalidate this test.

2. Verify requirement during MODES 3,4,5,6 or with core off-loaded.

Verify each DG operates for 2 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s:

18 months I

a. For 2 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded a 6900 kW and s 7700 kW; and

b. For the remaining hours of the test loaded a 6300 kW and s 7000 kW.

)

SR 3.8.1.15 NOTES

1. This Surveillance shall be performed within 5 minutes of shutting down the DG after the DG has operated 2 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded a 6300 kW and s 7000 kW. Momentary transients outside of load range do not invalidate this test.

2. All DG starts may be preceded by an engine prelube period.

Verify each DG starts and achieves:

18 months l

a in s 10 seconds, voltage 26480 V and frequency a 58.8 Hz; and

b. steady state, voltage 2 6480 V, and s 7150 V and l

frequency 2 58.8 Hz and s 61.2 Hz.

(continued)

COMANCHE PEAK - UNITS 1 AND 2 3.8-12 Amendment N0. 66

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AC Sources-Opertting 3.8.1 SURVElLLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY l

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SR 3.8.1.20 NOTE All DG starts may be preceded by an engine prelube period.

Verify when started simultaneously from standby 10 years condition, each DG achieves:

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a. in s 10 seconds, voltage 26480 V and frequency a 58.8 Hz; and

b. steady state, voltage 2 6480 V, and 5 7150 V and l

frequency 2 58.8 Hz and s 61.2 Hz.

SR 3.8.1.21 Calibrate BO sequencers.

18 months SR 3.8.1.22 NOTES

1. Verification of setpoint is not required.

2. Actuation of final devices is not included.

i Perform TADOT for Si and BO sequencers.

31 days on a STAGGERED l

TEST BASIS.

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COMANCHE PEAK - UNITS 1 AND 2 3.8-1 S Amendment No. 66 l

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Dhsel Fuel Oil, Lube Oil, End Starting Air i

L 3.8.3 Li 3.8 ELECTRICAL POWER SYSTEMS 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air l

LCO 3.8.3 The stored diesel fuel oil, lube oil, and starting air subsystem shall be ~

within limits for each required diesel generator (DG).

)

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l APPLICABILITY:

When associated DG is required to be OPERABLE ACTIONS NOTE Separate Condition entry is allowed for each DG.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more DGs with fuel A.1 Restore fuel oillevel to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months level between 74,600 and within limits.

86,000 gal in MODES 1-4 l

or between 65,600 and 75,000 in MODES 5 & 6 in l

storage tank.

j B. One or more DGs with lube B.1 Restore lube oilinventory 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months oilinventory less than a to within limits.

level 1" below the low run i

level but greater than a level 1" above the end of the lube oil dipstick.

(continued)

Amendment No. 66 COMANCHE PEAK - UNITS 1 AND 2 3.8-21

n c

DC Souro:s-Operating g,

3.8.4

' SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY 1

SR 3.8.4.2.

Verify no visible conosion at battery terminals and 92 days connectors.

QB Verify battery connection resistance is s 150x104 ohm for inter-cell connections, s 150xiO4 ohm forinter-rack connections, s'150x104 ohm forinter-tier connections, and s 150x104 ahm for tenninal connections.

SR 3.8.4.3 Verify battery cells, cell plates, and racks show no visual 18 months indication of physical damage or abnormal deterioration that could degrade battery performance.

SR 3.8.4.4 Remove visible terminal corrosion, verify battery cell to 18 months cell and terminal connections are clean and tight, and are coated with anti-corrosion material.

SR 3.8.4.5 Verify battery connection resistance is s 150x104 ohm 18 months for inter-cell connections, s 150x104 ohm for inter-rack connections, s 150x104 ohm forinter-tier connections, I

ands 150x104 ohm for terminal conriections.

(continued) 4 COMANCHE PEAK-UNITS 1 AND 2 3.8-25 Amendment No. 66

1 L-9 DC Sources-Operating 3.8.4 SURVElLLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.4.6 Verify each battery charger supplies 2 300 amps at 18 months a 130 V for a 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

SR 3.8.4.7 NOTES

1. The modified performance discharge test in SR 3.8.4.8 may be performed in lieu of the service test in SR 3.8.4.7 l

2. Verify requirement during MODES 3,4,5,6 or with core off-loaded.

Verify battery capacity is adequate to supp;y, and 18 months maintain in OPERABLE status, the required emergency loads for the design duty cycle when subjected to a battery service test.

(continued)

COMANCHE PEAK - UNITS 1 AND 2 3.8-26 Amendment No. 66

invirtirs - Operating 3.8.7

)

3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Inverters-Operating LCO 3.8.7 The required Train A and Train B inverters shall be OPERABLE.

NOTE inverters may be disconnected from one DC bus for s 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to perform an equalizing charge on their associated common battery, 1

provided:

a. The associated AC vital bus (es) are energized; and

b. All other AC vital buses are energized from their associated l

OPERABLE inverters.

APPLICABILITY:

MODES 1,2,3, and 4 i

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required inverter A.1 NOTE

' inoperable.

Enter applicable Conditions and Required Actions of LCO 3.8.9,

" Distribution Systems - Operating" with any vital bus de-energized.

Restore inverter to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

(continued)

COMANCHE PEAK-UNITS 1 AND 2 3.8-34 Amendment No. 66

,1

fD,

l RHR cnd Coolant Circulation - High Wat:r lev:1 l

l 3.9.5 3.9 REFUELING OPERATIONS

)

i 3.9.5 Residual Heat Removal (RHR) and Coolant CirculaUon High Water Level l

LCO 3.9.5 One RHR loop shall be OPERABLE and in operation.

l.

)

l NOTE l

The required RHR loop may be removed from operation for s 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 4

l 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period, provided no operations are permitted that would cause reduction of the Reactor Coolant System boron concentration.

s_

1 APPLICABILITY:

MODE 6 with the water level 2 23 ft above the top of reactor vessel flange.

i 1

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RHR loop requirements not A.1 Suspend operations immediately l

met.

InvoMng a reduction in reactor coolant boron concentration.

M l

A.2 Suspend loading immediately irradiated fuel assemblies in the core.

M (continued) l i

I I

l I

COMANCHE PEAK UNITS 1 AND 2 3.9-9 Amendment No. 66 l

l G

r-a RHR and Coolant Circulation - High Water level l

3.9.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME l

A. continued A.3 Initiate action to satisfy immediately L

RHR loop requirements.

1 A.4 Close all containment 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months penetrations providing i

direct access from l

containment atmosphere to outside atmosphere.

e SURVEILLANCE REQUIREMENTS l.

9 SURVEILLANCE -

FREQUENCY L

S R 3.9.5.1 Verify one RHR loop is in operation and circulating 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months reactor coolant at a flow rate of a 3800 gpm.

1-i-

l l

l l'

i COMANCHE PEAK - UNITS 1 AND 2 3.9-10 Amendment No. 66 s

l l'

l

p.

94

.f g D: sign Featur::s e

4.0

~ 4.0 DESIGN FEATURES (continued) 4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:

)

a.

Fuel assemblies having a rnaximum U-235 enrichment of I

5.0 weight percent; b.

k,, s 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 4.3 of the FSAR; c.

A nominal 9 inch center to center distance between fuel storage locations in high density storage racks; d.

A nominal 16 inch center to center distance between fuel asserablies placed in low density fuel storage racks, e.

New or partially spent fuel assemblies with a discharge bumup in the "2 out of 4 storage tilowed" region of Figure 3.7.17-1 may be allowed restricted storage in a checkerboard pattem in high density fuel storage racks or unrestricted storage in low density fuel storage racks; and f.

New or partially spent fuel assemblies with a discharge bumup in the "2 out of 4 storage not allowed" region of Figure 3.7.17-1 may be allowed restricted storage in an j

expanded checkerboard pattem (1 out of 4)in high l

density fuel storage racks or unrestricted storage in low density fuel storage racks.

J (continued)

COMANCHE PEAK - UNITS 1 AND 2 4.0-2 Amendment No. 66 5'

~~

p' L.

4 Progrcms and Mir;uals 5.5 L

l 5.5 Programs and Manuals (contir.uod{

L l

l 5.5.16; Containment Leakaos Rate Testina Procrem a.

A program shail te established to implement the leakage rate testing of -

the containment ta required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Ophon B, as modified by approved exemptions. This l

program shall be in accordance with the guidelines contained in '

r Regulatory Guide 1.163," Performance-Based Containment Leak-Test V

Program, dated September,1995" b.

The peak calculated containmen't infamal pressure for the design basis loss of coolant accident, P., is 48.3 psig.

. c.

The maximum allowable containment leakage rate, L., at P., shall be 0.10% of containment air weight per day.

. d.

Leakage rate acceptance criteria are:

1.

Containment leakage rate acceptance criteria is 51.0 L,. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria am < 0.60 L, for the Type B and Type C tests and s 0.75 L, for Type A tests; 2.

Air lock testing acceptance criteria are:

a)

Overall air lock leakage rate is 50.05 L, when tested at >

P,.

b)

For each door, leakage rate is 50.01 L, when pressurized to 2 P,.

e.

The provision of SR 3.0.2 do not apply to the test frequencies specified in l

the Containment Leakage Rate Testing Program, with the exception of

- the containment ventilation isolation valves.

f.

The provisions of SR 3.0.3 are applicable to the Containment Leakage

'. T w Rate Testing Program.

(continued) e l

l.

. COMANCHE PEAK - UNITS 1 AND 2-5.0-27 Amendment No. 66

,o

ty(.

g-s 4.;

f :.

RIporting Requirements

!jf 5.6

.m H

- 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements

- The foRowing reports shall be submitted in accordance with 10 CFR 50.4.

5$1

' Occuoational Radiation Exoosure Reoort 4

s NOTE A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.

I A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors), for whom monitoring was performed, receiving l

an annual deep dose equivalent > 100 mrems and the associated collective deep dose equivalen, (reported in person-rem) according to work and job functions (e.g., reactor op6. rations and surveillance, inservice inspection, routine maintenance, spec;st maintenance, waste processing, and refueling). This l

tabulation supplements the requirements of 10 CFR 20.2206. The dose assignments to'various duty functions may be estimated based on pocket ionization chamber, thermoluminescent dosimeter (TLD), electronic dosimeter, or film badge measurements. Small exposutus totaling < 20 percent of the individual total dose need not be accounted for. In the aggregate, at least 80 -

percent of the total deep dose equivalent received from extema! sources should be assigned to specific major work functions. The report covering the previous calendar year shall be submitted by April 30 of each year.

(continued)

COMANCHE PEAK - UNITS 1 AND 2 5.0 29 Araendment No. 66

ML20210N158

Text

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