Text

Amend 85 to License NPF-30,revises TS 3.3.2 & 3/4.8.1 to Add Mode 5 & 6 Applicability for Operability of Load Sequencer & Supplying 4 Kv Bus Undervoltage Circuits
	ML20058L959
Person / Time
Site:	Callaway
Issue date:	12/09/1993
From:	Wharton L; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20058L962	List: ML20058L959; ML20058L970;
References
	NUDOCS 9312200082
	Download: ML20058L959 (10)
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ug'o UNITED STATES

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8 NUCLEAR REGULATORY COMMISSION o

E W ASHINGTON, D. C. 20555 5

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UNION ELECTRIC COMPANY

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CALLAWAY PLANT. UNIT I t

DOCKET NO. 50-483 AMENDMENT TO FACILITY OPERATING LICENSE l

Amendment No. 85 License No. NPF-30 1.

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

i A.

The application for amendment filed by Union Electric Company (UE, the licensee) dated November 3,1992, and clarified December 1, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules i

and regulations set forth in 10 CFR Chapter I, B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the a

Commission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without _ endangering the health and safety of the public, and (ii) that such activities will be i

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-

}

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.

t 2.

Accordingly, the license is amended by changes to the Technical l

Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-30 is hereby amended to read as follows:

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9312200082 931209 PDR ADOCK 05000483!

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

85, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into the license. UE 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. The Technical Specifications are to be implemented within 30 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION p fA I44 L. Raynard Wharton, Project Manager Project Directorate III-3 Division of Reactor Projects II'/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance:

December 9,1993 i

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ATTACHMENT TO LICENSE AMENDMENT N0. 85 OPERATING LICENSE NO. NPF-30 QOCKET NO. 50-483 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contains marginal lines indicating the area of change. The corresponding overleaf page is also provided to maintain document completeness.

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REMOVE INSERT 3/4 3-19 3/4 3-19 3/4 3-20 3/4 3-20 3/4 3-20a 3/4 3-21 3/4 3-21 3/4 3-27 3/4 3-27 3/4 3-36(a) 3/4 3-36(a) 3/4 3-37 3/4 3-37 3/4 8-8 3/4 8-8 i

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.p TABLE 3.3-3 (COffrINUEDI EtiGINEERED SAFETY FEATUR_ES ACIVATION SYSTEM INSTRUMENTATION e

MINI?1UM e

TCTTAL NO.

OlA!!NELS OIA!!NELS APPLICABLE FUNCTIONAI, UNIT OF CilANUE_LE

'IU TRIP OPERABLE 20 DES ACTION

-e B.

Loss of Power a.

4 kV Bus Undervoltage 4/ Bus 2/ Bus 3/ Bus 1,

2, 3, 4, 5++,

6++

19*

-Loss of Voltage l

b.

4 My Bus Undervoltage 4/ Bus 2/ Bus 3/ Bus 1, 2, 3, 4, 5++,

6++

19'

-Grld Degraded voltage 9.

Control Room Isolation a.

Manual Initiation 2

1 2

All 25""

b.

Automatic Actuation 2

1 2

1, 2, 3, 4 26 w

Logic and Actuation

)

Relays (SSPS)

Y c.

Automatic Actuation Logic 2

1 2

All 26'"

g and Actuation Relays (r30P ESFAS) d.

Phase

'A' Isolation See Item 3.a above for all Phase "A*

Isolation initiatir'g functions and requirements.

7 10.

Load Shedder 2-1/ Train 1/ Train 2-1/ Train 1,

2<,

3, 4, 5+,

6+

25 g

Emergency Load Sequencer ct M

11.

Engineered Safety Features Actuation System Interlocks E

a.

Pressuriser Pressure, 3

2 2

1,2,3 20 P-11 enI b.

Reactor Trip, P-4 4-2/ Train 2/ Train 2/ Train 1, 2, 3 22

TABLE 3.3-3 (Continued)

TABLE NOTATION Trip function may be blocked in this MODE below the P-11 (Pressurizer Pressure interlock) Setpoint.

Trip function automatically blocked above P 11 and may be blocked below P-11 when Safety injection on low steam line pressure is not blocked.

Trip function may be blocked just before shutdown of the last operating main feedwater pump and restored just after the first main feedwater pump is put into service (following its startup trip test).

The provisions of Specification 3.0.4 are not applicable.

One in Separation Group 1 and one in Separation Group 4.

The de-energization of one train of BOP ESFAS actuation logic and actuation relays renders two of the four channels inoperable. Action Statement 21 applies to both Functional Units 6.c and 6.g in this case.

The provisions of Specification 3.0.4 are not applicable in Modes 5 and 6.

+

Only the shutdown portion of one sequencer is required to be OPERABLE in Modes 5 and 6 which corresponds to the OPERABLE Emergency Diesel l

Generator.

++

Operability is only required for associated OPERABLE bus in Modes 5 and 6.

ACTION STATEMENTS ACTION 14 -

With the number of OPERABLE channels on less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-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 ; however, one channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1, provided the other channel is OPERABLE.

ACTION 15 -

With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed until performance of the next recuired ANANLOG CHANNEL OPERATIONAL TEST provided the inoperable channelis placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 16 -

With the number of OPERABLE channels one less than the Total Number of Channels, operation my proceed provided the inoperable channel is placed in the bypass condition and the Minimum Channels OPERABLE requirement is met. One additional channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1 s

ACTION 17 -

With less than the Minimum Channels OPERABLE requirement, operation may continue provided the containment purge supply and exhaust valves are maintained closed.

CALLAWAY - UNIT 1 3/4320 Amendment No. 26,H,5)#5

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TABLE 3,3 3 (continued)

ACTION STATEMENTS (continued)

ACTION 18 -

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-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 COLO SHUTOOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 19 -

With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or-POWER OPERATION may i

proceed provided the following conditions are satisfied:

a.

The inoperable channelis placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , and b.

The Minimum Channels OPERABLE requirement is met:

however, the inoperable channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing of other channels per Specification 4.3.2.1.

ACTION 20 -

With less than the Minimum Channels OPERABLE, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months determine by observation of the associated permissive annunciator window (s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.

ACTION 21 -

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTOOWN within the fo!!owing 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months s: however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1 provided the other channelis OPERABLE.

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ACTION 22 -

With the numbr: of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANOBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTOOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 23 -

With the number of OPERABLE channels one less than the Total i

Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the associated valve inoperable and take the ACTION required by Specification 5.7.1.5.

ACTION 24 -

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, declare the affected auxiliary feedwater pump inoperable and take the ACTION required by Specification 3.7.1.2.

r CALLAWAY - UNIT 1 3/4 3-20a Amendment No. 95 P

9

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I TABLE 3,3 3 (continued)

ACTION STATEMENTS (continued) l ACTION 25 -

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, declare the affected di3sel generator and off-site power source inoperable and take the ACTION required by Specification 3.8.1.1 or 3.8.1.2.

'i ACTION 26 -

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement,1estore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or initiate and maintain operation of the Control Room Emergency Ventilation System.

ACTION 27 -

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s: however, one channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1 provided the other channelis OPERABLE.

f (NOTE: ACTION STATEMENTS 28 THROUGH 31 ARE LOCATED ON OTHER TABLES.)

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CALLAWAY - UNIT 1 3/4 3-21 Amendment No. fA,85 i

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TABLE 3.3-3 (Continued)

)

ACTION STATEMENTS (Continued)

ACTION 32 - With the number of OPERABLE channels one less than the Total I

Number of Channels, except for testing, STARTUP and/or POWER OPERATION may proceed for up to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months provided the following conditions are satisfied:

a.

The inoperable channel is placed in the tripped condition l

within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and b.

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels per Specifica-tion 4.3.2.1.

Restore the inoperable channel to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

With the number of OPERABLE channels one less than the Total Number of Channels due to testing of a channel, that channel may be tripped for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1.

ACTION 33 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a.

The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and b.

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels per Specifica-tion 4.3.2.1.

ACTION 34 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE.

l ACTION 35 - With an inoperable delay timer in the Trip Time Delay circuitry.

l STARTUP and/or POWER OPERATION may proceed provided that the Vess'el AT (Power-1, Power-2) channels in the affected protection-sets are placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

l CALLAWAY - UdIT 1 3/4 3-21(a)

Amendment No. /3,64 f

O TABLE 3.3-4 (COffrINUEDL t~g

$NGINEERED_ SAFETY FEAnfRES ACI13ATION SYSTEM INSTRUMEtrTATION TRIP __SETPOIftrS TOTAL SEtISOR TRIP ALIDWABLE FUNCTIONAff_ UNIT ALLOWA! ICE (TA_l ERROR (S)

SETPOIttr VALUS c-5 8.

Loss of Power (Continued)

--4 b.

4 kV Undervoltage

-a

- Grid Degraded Voltage N.A.

N.A.

104.5V 104.5+2.6,-0V (120V Bus)

(120V Bus) w/129s delay w/119111.Es delay 9.

Control Room Isolation a.

Manual Initiation N.A.

N.A.

b.

Automatic Actuation N.A.

N.A.

Logic and Actuation Relays (SSPS)

N c.

Automatic Actuation N.A.

N.A.

Logic and Actuation y

Relays (BOP ESFAS) d.

Phase "A"

Isolation See Item 3.a. above for all Phase "A"

!aolation Trip Setpoints and Allowable values.

10.

Load Shedder Emergency N.A.

N.A.

Load Sequencer F

m 11.

Engineered Safety E

Features Actuation g

System Interlocks a.

Pressurizer Pressure, N.A.

N.A.

1 1970 psig s 1981 psig g

P-11 sa b.

Reactor Trip, P-4 H.A.

N.A.

w (It

TABLE 3.3-4 (Continued)

TABLE NOTATIONS

" Time constants utilized in the lead-lag controller for Steam Pressure-Low are t > 50 seconds and T2 1 5 seconds. CHANNEL CALIBRATION shall ensure that these time constants are adjusted to these values.

- The time constant utilized in the rate-lag controller for Steam Line Pressure-Negative Rate-High is greater than or equal to 50 seconds. CHANNEL CALIBRATION shall ensure that this time constant is adjusted to this value.

I i

CALLAWAY - UNIT 1 3/4 3-28

c

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r-Q, TABLE.4.3-2 (Continued).

E, N

ENGINEERED _ SAFETY FEATURES ACntATION SYSTEM _ INSTRUMENTATION SURVEILLANCE REOUIREMENTS E-TRIP MODES y

ANALOG ACIUATING FOR WHICN CHANNEL DEVICE MASTER SIAVE SURVEILIANCE CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACIUATION REIAY REIAY IS FUNCTIONAL UNIT QiEf,E CALIBRATION TEST TEST LOGIC. TEST _ TEST..

TEST BBQ11LR_EQ '

6.

Auxiliary Feedwater (Continued) f.

Loss-of-Offsite Power N.A.

R N.A.

M N.A.

N.A.

1, 2, 3

[

g.

Trip of All Main N.A.

N.A.

R N.A.

N.A.

1, 2

Feedwater Pumps

. h.

Auxili'ry Feedwater S

R M

N.A.

M.A.

N.A.

1, 2, 3 Pung Suctlon Pressure-Low 7.

Automatic Switchover to R

Containment Surnp Jm to a.

Automatic Actuation N.A.

N.A.

M(1)

Q(3) 1,2,3,4 d,

Logic and Actuation R

Relays (SSPS) i b.

RWST Level - Low Low S

R Q

M.A.

N.A.

N...

1, 2, 3, 4 Coincident With-Safety Injection See Item 1 above for all Safety Injection Surveillance Requirements.

8.

Loss of Power N

a.

4 kV Undervoltage-N.A.

R N.A.

M N.A.

N.A.

1, 2, 3, 4,

5++,

y Loss of Voltage 6++

to5 b.

4 kV Undervoltage-N.A.

R' N.A.

M N.A.

N.A.

1, 2, 3,

4, 5++,

j Grid Degraded Voltage z

6++

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~ INSTRUMENTATION 3/4.1.3 MON!TORING INSTRUMENTATION RADIATION MONif0 RING IOR PLANT OPERATIONS ~ \\ LIMITING CONDITION FOR OPERATION

3.3.3.1 The radiation monitoring instrumentation channels for plant operations shown in Table 3.3-6 shall be OPERABLE with their Alarm / Trip 5etpoints within the specified limits.

APPLICABILITY: As shown in Table 3.3-6. ACTION: With a radiation monitoring channel Alarm / Trip 5etpoint for plar.t a. operations exceeding the value shown in Table 3.3-6, adjust the Setpoint to within the limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or declare the channel inoperable. b. With one or more radiation monitoring channels for plant operations inoperable, take the ACTION shown in Table 3.3-6. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. c. SURVEILLANCE REQUIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel for plant' operations shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST for the MODES and at the frequencies shown in Table 4.3-3. O CALLAWAY - UNIT 1 3/4 3-38 q__ TABLE 4.8-1 DIESEL GENERATOR TEST SCHEDULE # NUMBER OF FAILURES IN NUMBER OF FAILURES IN LAST 20 VALID TESTS

or LAST 100 VALID TESTS

TEST FREQUENCY

<1 -<4 At least once per 31 days -> 2** >5 At least once per 7 days 1

The most limiting test frequency should be applied from the two columns of l

this table.

Criteria for determining number of failures and number of valid tests shall be in accordance with Regulatory Position C.2.e of Regulatory Guide 1.108, Revision 1, August 1977, but determined on a per diesel generator basis.

l l For the purposes of determining the required test frequency, the previous test failure count may be reduced to zero if a complete diesel overhaul to like-new conditions is completed, provided that the overhaul, including appropriate post-maintenance operation and testing, is specifically approved by the manufacturer, and if acceptable reliability has been demonstrated. The reliability criterion shall be the successful completion of 14 consec-utive tests in a single series. Ten of these tests shall be in accordance with Specification 4.8.1.1.2a.4) and 4.8.1.1.2a.5); four tests in accordance with Specification 4.8.1.1.21. If this criterion is not satisfied during the first series of tests, any alternate criterion to be used to transvalue the failure count to zero requires NRC approval.

- The associated test frequency shall be maintained until seven consecutive failure free tests have been performed and the number of failures in the last 20 valid tests has been reduced to one.

CALLAWAY - UNIT 1 3/4 8-7 Amendment No.21 ELECTRICAL POWER SYSTEMS A.C. SOURCES SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.1.2 As a minimum, the following A.C. electrical power sources shall be OPERABLE: s. One circuit between the offsite transmission network and the Onsite Class 1E Distribution System, and b. One diesel generator with: 1) A day tank containing a minimum volume of 390 gallons of fuel, 2) A fuel storage system containing a minimum volume of 85,300 gallons of fuel, and 3) A fuel transfer pump. APPLICABILITY: Modes 5 and 6. ACTION: With less than the above minimum required A.C. electrical power sources OPERABLE. immediately suspend all operations involving CORE ALTERATIONS, positive reactivity changes, movement of irradiated fuel, or crane operation with loads over the spent fuel pool. In addition, when in Mode 5 with the reactor coolant loops not filled, or in Mode 6 with the water levelless than 23 feet above the reactor vessel flange,immediately initiate corrective action to restore the required sources to OPERABLE status as soon as possible. SURVEILLANCE REQUIREMENTS 4.8.1.2 The above required A.C. electrical power sources shall be demonstrated OPERABLE by the performance of each of the requirements of Specifications 4.8.1.1.1,4.8.1.1.2 (except f or Specifications 4.8.1.1.2a.5), and 4.8.1.1.2f.5), 6),

10) and 12) for the LOCA sequencer portion of LSELS only), and 4.8.1.1.3.

l CALLAWAY - UNIT 1 3/4 8 8 Amendment No. 85 i

ML20058L959

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